05000334/LER-1980-055-01, /01P-0:on 800811,all Three Reactor Coolant Loop RTD Manifolds Determined to Be Overstressed During Seismic Event at Respective 2-inch to 3-inch Reducers.Cause Unknown. Each Line Will Be Reinforced by Anchors

/01P-0:on 800811,all Three Reactor Coolant Loop RTD Manifolds Determined to Be Overstressed During Seismic Event at Respective 2-inch to 3-inch Reducers.Cause Unknown. Each Line Will Be Reinforced by Anchors

ML19338C674
Person / Time
Site:	Beaver Valley
Issue date:	08/12/1980
From:	Lacey W DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19338C673	List: 05000334/LER-1980-053-01, /01P-0:on 800811,significant Overstress Condition on Charging Lines Found Possible During Seismic Event.Caused by Inadequately Sized U Bolts.Bolts Will Be Replaced with 3-inch Pipe Clamp.Support Will Be Modified 05000334/LER-1980-054-01, /01P-0:on 800811,significant Overstress Condition Found Possible on Safety Injection Line from High Head Safety Injection Pumps to Reactor Coolant Sys Hot Legs, During Seismic Event.Caused by Inadequate Weld 05000334/LER-1980-055-01, /01P-0:on 800811,all Three Reactor Coolant Loop RTD Manifolds Determined to Be Overstressed During Seismic Event at Respective 2-inch to 3-inch Reducers.Cause Unknown. Each Line Will Be Reinforced by Anchors 05000334/LER-1980-056-01, /01P-0:on 800811,discovered That Significant Overstress Condition on High Head Safety Injection Lines to Respective Hot Lines Could Occur During Seismic Event.Caused by Inadequately Sized U Bolts & Undersized Weld Supports ML19338C672
References
LER-80-055-01P, LER-80-55-1P, NUDOCS 8008180402
Download: ML19338C674 (1)

LER-1980-055, /01P-0:on 800811,all Three Reactor Coolant Loop RTD Manifolds Determined to Be Overstressed During Seismic Event at Respective 2-inch to 3-inch Reducers.Cause Unknown. Each Line Will Be Reinforced by Anchors

Event date:
Report date:
3341980055R01 - NRC Website

text

.-

O tyQ m.can mm on rvn fu. ctou aro.uonts,e.,i cdmtaos noco i 1

1 I

i le 1 A l a It i s t i l@l o 10 l-10 lo lo lo lo I-10 to l@i' 11 11 11 (11@u l r

..g m a -..

a

.u s....,

v m... u.

"O Lt B..o i s t o l o 1 o 12121' Gi o l a l' l '.1 a f o 83)f o f a t o.

.u m., m..

evta,Y of scanenow Ano anosaet.a co stoutwets @ ifolds have been determined to he overstrense loop RTD man l l All three Reactor Coolant Loss of this line durint a seinste event at their respective 2 to 3" reducers.

lt Breaks of this afre f

) I would constitute a 2" or 3" LOCA depending on break Incation.

j i have been considered in the SAR and core protection has been provided.

t If

)'

{ Cl Ji@ U. @.2Nlll.y @ l E l U l P l o f R l Tj @.Jil

.W.,

I

'"."s" il :"

- = coes El

)

s.

e ee u

u

.e sc &

"* "n Y

b n

"ivew,vsaa O =sg. c:J,81 J p

Lol 515J W ff 12 j VJ p

pJ ww

.. m 2..

gasgue p.ie gae !@oi ei o-e,j p e,=g u= e. =L. p etz i m n

=m

.=,

- x w CAust otscfierTicas Awo countenvt Acnoess for the lines being overstressed.

Each

] [ Co cause descriptf on is known at present i

h t line will be reinf'orced by installation of snchorn an their respective 2" lines to I

All work. will be done prior to startup.

A l

] I relieve the overr. tressed condition, I) I final r-1rt will be subaiteed upon completion of this studv.

i 3t

'.Vic M.'

oe. v.n. @

E'.Ell5#

.e r

Sweet =1 tave=tieatio=

) Lttl@ !oIoIol@lDe=ica I

L.c_l@l

%. g,,,,

n g ; canon o, tc. @

.ne.u

~w menen

] u.

LIFBI N/A I

I r/A LL]

,let..,.a..

3 I o I o I o l@li}@i ~1.o w.n..

o N/A a*~ ~.i'~v.

') IoloIo $ ei -. O w.

N/A e,

- s to 08 omoav saogiry

(

) di N/A e

ev unc w on.LY

"'*Ells*1.o @

i f__ I t i i i i i ' I ' '

!! L,1f61 ma N/A m

~

412-M 3-8525 W. S. taccr et emuc os enti.wn 0-8008180YOA'