05000346/LER-1979-068-03, /03L-0 on 790623:during Performance of Svc Water Sys Monthly Test ST 5075.01,component Cooling Water Heat Exchanger 1-3 Outlet Valve Failed to Close Fully.Caused by Vibrational Loosening of Retaining Nut

From kanterella
(Redirected from ML19242A144)
Jump to navigation Jump to search
/03L-0 on 790623:during Performance of Svc Water Sys Monthly Test ST 5075.01,component Cooling Water Heat Exchanger 1-3 Outlet Valve Failed to Close Fully.Caused by Vibrational Loosening of Retaining Nut
ML19242A144
Person / Time
Site: Davis Besse 
Issue date: 07/19/1979
From: Deakyne K
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19242A141 List:
References
LER-79-068-03L, LER-79-68-3L, NUDOCS 7907310373
Download: ML19242A144 (3)


LER-1979-068, /03L-0 on 790623:during Performance of Svc Water Sys Monthly Test ST 5075.01,component Cooling Water Heat Exchanger 1-3 Outlet Valve Failed to Close Fully.Caused by Vibrational Loosening of Retaining Nut
Event date:
Report date:
3461979068R03 - NRC Website

text

U. S. NUCLE AR REGUL ATo81Y COMMISSloN NRC FORM 306 U 77)

LICENSEE EVENT REPORT CONTHOL BLOCK: l l

l l

l l

l (PLEASE PRINT OR TYPE ALL REQUIRED !NFORMAllON) 1 6

@l j@

l 0 0 Nl P! F 0l 3l@l4 1

1 l1 1

l Ol 11 D jB lS l1 @l0l0 Io i

8 3 LICENSEE CODE 14 la LICE %E NUYeEH 16 26 L IC t ".)E TvPE JJ

$1 LAI 'A CON'T

[",' l L @l 0 l 5 l 0 l-l 0 l 3 l 4 l 6 Ql 0 ] 6 l 2 3 ]7 19 l@l 0 l 7 l I l o l 7 l 9 j@

lo i

S 60 61 COC k. E T ' s '. S E R M

6)

EVENT DATE I4 lb HEP 0HTT 60 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h oi2 l On June 23, 1979, at 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br /> during the performance of the Service Water (SW) SYs-1

o i l ten Monthly Test ST 5075.01, it was found that SW 1429, the Component Cooling Water I

o l (CCW) llea t Exchanger 1-3 SW Outlet Valve, f ailed to consistently go to the f u l lv__c_Innj d po s i t io n.

As the unit was in Mode 5 at the ti:,e of the occurrence, no action state-I

g ;s y o

6 l ment was applicable. This report is being submitted as documentation of a comganent 1 0

7 l failure. There was no danger to the health and sa.ety of the public or station per-l lo a l sonnel.

There were two loops of CCW available for operation at the time of occurroned.

n 7

8 9 C O*.' P VALVE (SP-33 74)

SYST E M C AUS E

CAUSE

CODE CODE SU9CCOE COYPONENT CcDE SUCCODE SUBuCCE lolol I W I B l@ l al@ l n @ l v l a l t i v i o l e l@ l nl@ LnJ @

7 8

9 to 11 12 13 18 13 20 SEQUEN TI AL OCCUP AE NCE REFOHT REVICON EVENT (E AR REPORT NO CODE TYPE No.

@ ay.=Ha 17191

- l 1016 81 l/l 10131 L'J I-1 101 LE R 21 22 23 24 26 21 23 2'J Ju 31 32 ACTION FUTUHE ErrE

e

' " ^ ^ -

^

av, W 'FNT NP84n 4 PD I Y E CO*.'P t'O U PO*; E *i T TA<EN ACTION ON Pt A *,7

rTHQ3 HOURS 1R1 SUHYtTTED FOHMaub SU PP LI C H MANUFACTLREH R

31 4Q 41 42 43 44 4/

24 a

33 cAUSE DESCRIP TION AND CORRECTIVE ACTIONS h l Slippage and misalign-ent of the valve linkage of 5414;9 was due to a vibrational i

o ji I,j loosening of a retaining nut.

A visual iTisnection of the service water outlet valverI i,

7 l on all three CCW heat exchangers was made and,alve SW 1424 was realiened and recali-1 i

3 l brated in addition'to SW 1429 as a precautiona y mersure.

Previously nrenared Faci-l yil4; l lity Change Request 79-151..a s ?plemented_c i al l three valves to nrevent r e en t r e n c e._.]

i s o METHOD OF F ActLITY STATUS NPOAEH OTHE R ST ATUS 015CO VE H Y DISCU /f RY DESCH'P TION n

l B l@! Surveillance Test ST 5075.01 l

lG @l0 0l 0]@l NA i

s AC. T iVI T Y CO" TENT RE LE AsED Of HELEASE AVOUNT OF ACTivlTV L OC ATION Cr ret E ASE i

6 2

l2I NA NA f

PO I

8

'J 10 11 44 45 h

.tE

< E DE;;HipflON feg i M (S. f S.

!i 5 h @

l lil7l 0l0 2l lNA II ' t ',.

'd PEHSON NE L INJu ES

%;veEn CEER PTION l0l0l0 @ NA j

i

$F'Nbd!"""@

7 907 310W

  1. _J l ' I o f Lz J@l N^

gc 1

H

')

10

" " w' "3

,; % " ECH,PraN @

NA I

IIIIIIIIIi l ll I21oIULj31 a co a.2 a 2 io g

DVR 79- 090 N AYE OF PHEPARE R'

_Deakvne b b) # !

) IL PHONE- 039-250-5(309-I' "

210

e TOLEDO EDIS05 CO."PANY DAVIS-EESSE NULLEAR POUER STATION UNIT ONE SUPPLEMENTAL INFOR'uTION FOR LER NP-33-79-74 DAT'i 0F EVENT: June 23, 1979 FACILITY:

Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:

Component Cooling Uater Heat Exchanger 1-3 Service Water Outlet Valve SW 1429 operating imptcperly Conditions Prior to Occurrence: The unit was in Mode 5, with Power (MUT) =

0, and Load (Gross MWE) = 0.

Description of occu ence: On June 23, 1979, at 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br />, during the perf ormance of Service Uater Systen Monthly Surveillance Test ST 5075.01, SW 1429, Conponent Cool ing Uater (CCU) Heat Exchanger 1-3 Service Water (SU) Outlo-Valve failed to consistently provide a close indication. Visual inspection revealed the valve was not going to the fully closed position. The operator suspeneded the surveillance test, and submitted a work request. As the unit was in Mode 5 at the t:.me of the occurrence, no action statement was

,+11 cable. This report is being submitted as documentation of a com-ponent failure.

Designation of Apparent Cause of Occurrence:

ine improper operation of valve 5W 1429 was attributed to slippaae and misalignment oi the valve linkage. This was caused by a design deficiency which allowed vibrations to 1 cosen the bolt that re ta ins the twc linkage anns tecether.

Analysis of Occurrence: There was no dangc_ to the health and saf ety of the public or station personnel.

There were two loops of component cooling water available for opera-tion at the time of occurrence.

Corrective Action

' The valve linkage was realigned and calibrated under Maintenance Work Order IC-309-79.

As a precautionary measure, the linkage for SU 1424, CCU Heat Exchanger 1-1 SU Outlet Valve, uas recalibrated under the same maintenance work order.

A visual inspection of T.

1434, CCW Heat Exchanger 1-2 SW Outlet Valve, was performed and it was determined that recalibration would not be necessary due to a recent cali-bration performed on April 4, 1979 under Maintenance Work Order IC-223-79.

The applicable sections of ST 5075.J1 vere successfully performed to verify the opera-bility of the valves.

On July 3, 1979 implementation of previously prepared Facility Change Request (FCR)79-151 was completed.

This FCR modified the linkages to prevent vibrations f rom loosening the retaining bolt on all three valves.

Failure Data: There have been three previously reported occurrences of actuator inoperabilities of a service water valve. The inoperabilities reported in Licensee Event Report NP-33-78-120 were caused by a nut missing on the actuator.

Licensee LER #79-068

/* I

  • 7l1 4.

l TOLEDO EDISO:: COMPA'iY I

DAVIS-EESSE !!UCLEAR P0b'ER STATIO: I";IT 0 JE 5

SUPPLEME::TAL I:;FOR:tATIO:i FOR LER !!P-33-79 -74 PAGE 2 Event Report :;P-33-78-ll was caused by a failure of a solenoid valve, and Licensee Even t Report ! P-33-78-147 was caused by vibrations loosening the bolt retaining the two linkage arns.

LER #79-068 s

I yd

^{ [3

\\

ie

j