ML19344E663

From kanterella
Jump to navigation Jump to search
LER 80-123/03L-0:on 800812,during Normal Operation,While Performing Reactor Core Isolation Cooling Steam Line Pressure Instrument Functional Test,Outboard Isolation Valve Failed to Fully Close.Caused by Defective Torque Switch
ML19344E663
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 08/29/1980
From: Nix R
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19344E658 List:
References
LER-80-123-03L, LER-80-123-3L, NUDOCS 8009020433
Download: ML19344E663 (2)


Text

C

  • LICENSEE EVENT REPORT Q

CONTROL BLOCK: l

-1 l l 'l l l lh 6

(PLEASE PHINT OH TYPE ALL 11EQUIRED INF ORMATioN) 0 t InlA l E ll lit 1214l@l150 lo l 10101010'l0 l- l010 l@l4 Il 11 11 lj__}@lb/ CAI LICLNSE TYrg JO l

!W l@

LICEN5E NUMBEH 25 26 7 8 9 tiCENSEE CODE

- CON'T 101il C"c' l60L l@l69 0 l 510 l 010 l 3 l 616 ta l@l01811 69 EVENT DATE l21810 l@[ 14 74 018l ftE PORT 21DATE91 8lt!0Ol@

7 -8 DOCKET NUMBE fl EVENT DESCRIPTloN AND Pf tODADLE CONSEQUENCES h lo l2l l During normal operation, while performing HNP-2-3409, RCIC Steam Line I o 3 'l -Pressure Instrument Functional Test, 2E51-F008, Outboard Isolation Valve l O 4 l failed to fully close. The RCIC. inboard steam supply line isolation l valve, 2E51-F007, was closed per Tech Spec 3.6.3.a. The HPCI system was l l O [ .cl l IO is i l operable. There were no effects upon public health and safety due '.o l

[ TTY 1I this event. This was a repetitive occurrence as last reported on Report- l LO is i g able. 0ccurrence Report No. 50-366/1980-055. 1 DE CODE S BCO E COMPONENT CODE SUBC dE SU OE 7

O 9 8

l C l E l@' 11O@ l Al@ l V l Al L i V I 01 P l@ [B_J@

9 to 12 13 18 19 lZ 20 l@

SEQUE NTI AL OCCURRENCE REPORT REVISION EVENT YE Aft REPORT NO. CODE TYPE N O.

L E B RO

@ ujg,T,r 18 10 l [ _j l 11 21 31 l/l 10131 lL l l-l [0_j 32

._21 22 23 24 26 27 28 29 30 31 AK N AC 0 ON LP7 MET 4 HOURS 22 S I F R1 B. SUPPLI MAN F CTUfER (B j@l1,_j@ l_Zj@ l36Zl@ l0-10 l0 lu l l41 Yl@ [_fij@ lN l@ l44L l 2 l 0 l 047l@ '

33 34 3d 31 40 42 43 CAUSE oESCRIPTloN AND CORRECTIVE ACTIONS

[TTF1 1 An investigation into the failure of the valve to fully close revealed I i i l that the torqueswitch was defective. The torque switch, that stops the l

, 2 l valve when it is fully closed, was opening prior to the valve reaching l

( 3 -l a fully closed position. The torque switch was replaced and procedure l IINP-2-3409 was then performed satisfactorily. I ml STA S  % POWEft OTHER ST ATUS ISCO R DiSCOVEftY DESCRIPTION i t, W@ l '0l 9l 9l@l NA .l [_Bj@l Operator observation l AEnviTY ~ CO0 TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE i e NA l l NA l LZ_l @ 'lZ- J@l * * "

PtnsONNEL ExPOSMES NUM8E f4 TYPE DESCRIPTION Q 10l010l@lZl@l-NA l

' PERSONNEt iN;Un'iES NUMBER DESCRIP TION i n l0l0l0l@l NA l

7 8 9 . 11 12 80

'#PE "iESC

  • T#1 ION' ' '**' " @ -

i o [Zj@l 'NA l

A; PunuSTY DESCRIPTION , .8'009020 D ) Nnc ute oNov

  • ISSUE D 2 O LnJ81- -

NA' I 11ll11lllllll5

<-7

~

,8 U- to a 68 69 80 ti; L NAME OF PREPARER D T Niv. Suot. Of flaint . PHONE: 912-367-7701 .

L HARRATIVE REPORT I Georgia Power Compar.y Plant E. I. llatch Baxley, Georgia Reportable Occurrcnce Report No. 50-366/1980-123. I On August 12, 1980, with the reactor at 99% power, the Outboard Steam Line  :

Isolation Valve, 2E51-F008, failed to fully close while performing the RCIC  !

Steam Line Pressure Instrument functional Test. The Inboard Steam Supply l Line Isolation Valve, 2E51-F007, was closed per Tech Spec 3.6.3.a. This l was a repetitive event as last reported on Reportable Occurrence Report i No. 50-366/1980-055.  !

.The cause of (Nie valve failure was due to a driective torque switch. This  ;

torque switch, which stops.the valve when it .s fully closed, was opening l prior to the valve reaching the full closed pasition. The torque switch i was replaced and the RCIC Steam Line Pressure Instrument Functional Test performed satisfactorily. ,

Although the 2E51 F008 valve would not fully closa during this test, it would open and the RCIC system could have auto-started had it been needed.  ;

The ilPCI system was also operable during this time.

Due to the number of valves at Plant Hatch, with only occassional torque switch failures, this problem does not appear to be generic.

Public health and safety was not affected by this incident nor was there any effect upon safe plant operation.

5 9