05000366/LER-1980-012-03, /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports

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/03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports
ML19296D416
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 02/26/1980
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19296D409 List:
References
LER-80-012-03L-01, LER-80-12-3L-1, NUDOCS 8003040555
Download: ML19296D416 (2)


LER-1980-012, /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports
Event date:
Report date:
3661980012R03 - NRC Website

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.reysea"[g oIa U..'h il e oaera tina at es sen tiallv full nowe r, i t was determined _that_the_RHR_and_P_lant 1

oi3; [ service wa hr minir'r flrw lines !are inadequate 1v supported.

A computer analysis 1

F5Til [ of the exic.tinc arr'gcer?nt revnaled that the existinnupports_[andors 2E11-RSb'-

I o 3; < A E6 a n d 2 P a l-I S'..' W. I wo ul d fa i l i f subjected to the design seismic loads.

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l a non-repetitive occurrence for ttie RHR and Plant service water Dining.

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Desian Chanae Request 79-60 i

i and Mai n tenance ilegs ts 2-00-733 and 734 were iimlemented adding the supports I

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. 1. Hatch Ea x1 - /, Goorri a 31513 ReN r ble Occurrence Ponort "o.

50-366/1980-012 On 1;rua ry lo,1990, a t 1E00 C3T, the Hatch Unit 2 reactor was at steady-star >.ne ra t i nn (?d2R int).

The plant was contacted by the architect-eMi: :>er about a seismic loading problem with the RHR service water and Picnt nrrvico water cioina supporto A computer analysis of the existing arr nrement of the RHR and Plant service water minimum flow line pipe supoorts revealed that anchors 2E11-RS',-AP6 and 2P41-ISW-A34 would fail if the system was sut>jected to the design based seismic laads.

This event does not directly affect the Unit I system since it is supported differently.

This is a non-repetitive occurrence for the RHR and Plant service water Th m r>

nn effer" u nn nunlic health and safety due to this T c,o

c.. i c v e. p g,..le re avallanie and enerable during this time.
- or ne owe t was anuarertiv s c sinn deficiency.

The architect-r e e s lonea rno sysrAm so tna t tre ancnors would oe installed at

'; ten ia i n mur, rlow lint, but tr.e ;)10ing sucport installation

> ca s t eu for tr 2 ancnors to ne instailec 13 feet - 9 inches from u; toe i ine, as tney were actuai iv ins talled.

Design Change

<9-oa anc naintenance nequests 2-to-733 and 734 were implernented

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u to acd two accitional supports so that the related piping and

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is uouia witnstand tne design based seismic loads.

The new supports ar cresen tly in place and the sys tems have been returned to service.

No further reporting is required.