ML19325D246

LER 89-010-00:on 890920,reactor Tripped Manually Following Loss of Operating Steam Generator Feed Pump.Caused by Inadvertent Opening of Overspeed Trip Test Valve.Individual Involved in Event Counseled to Be More aware.W/891012 Ltr

ML19325D246
Person / Time
Site:	Farley
Issue date:	10/12/1989
From:	Hairston W, Dennis Morey ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-010, LER-89-10, NUDOCS 8910190282
Download: ML19325D246 (4)

Text

- . ,

q

.c, -v ,

g.m ,

f

' ' ~

+

', ,e .

lc > j" + -' "!g

. - Nabama Powsc Company' -

' .. ? 40 inwrness Center Parkway ,

t i , 's  ;

a; b f '

Post Office Box 1295 .

L. 4

• Birmingham, Alabama 35201 .;

[ , Telephone 205 868 5581 L '

t. '

4 . W. G. Hairston, til :

' Senior Vice President - -

1

. Nue: ear Operations Alabama Power -

[; e ' October 12,'1989 tre sourtan derric system 10 CFR 50.73

)

.g . Docket No. 50-364.

U. S.' Nuclear Regulatory Commission '

ATTN: Document Control Desk '

Vashington', D.C. 20555

Dear Sir ,

i Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report No. LER 89-010-00

• Joseph M. Farley Nuclear Plant, Unit 2, Licensee Event Report No. LER 89-010-00 is being submitted in accordance with 10CFR50.73.

t

, t If you have any questions,'please advise.

Respectfully submitted,

._ s .l

h. , '# 9~

j V. G. Hairston, III  ;

i-  ;

-VGH,III/ JAR .nd 8.32 j

. Enclosure 4 -

cc: Mr. S. D. Ebneter Mr. G. F. Maxwell

')

y u

s A i .K (( ,

i t

._ $ ; -

• a ,

.no  ;

11 ORM3eg. U.S. NUCL E A l i t1ULATMV COMMISSION d.PPHOVED oms NO. 31600104 A . . f KPt%ES 4/30,02 .

tsTIMATED BUADEN PER RESPONSE TO COM7LY WTH THr$

LICENSEE EVENT REPORT (LERl '"l&"f8'Un*ARoE.'U%d'N Es'!S8t TNit R/COES C ,

' " "^ "

O!UI?o"R! '

s'MM,i!"A"'W S', tilt #a fddT"

, THE PAPERWORK REDUCTION PROJECT 13160 4104 . OF FICt OF M ANAGE ME NT AND BUDGE T, W AbHINGTON. DC 20503.

I, P ClLITVsepa84 Hi DOCati NUMOGR Qi FAGE 93 .

Joseph M. Farley - Unit 2 og5,o,o,o,3,6p 3yv ,.3 IlTLE64)-

J Reactor Trip Caused By Inadvertent Opening Of The Overspeed Trip Test Valve

$ VENT DAf t (El LIR NUMBER 16) REPORT DAf t 171 OTMitIl F ACILITitS INVOLVED (St

~

l} MONT w oAv vtAR vtAR o=

, '4,6  :=;ag MONTn oAv vtAR .acisiTva. Mis pocati NUMet aisi 01 6101010 1 1 1 0 89 - - C0 -

n. 2] 0 8l 9 0l1l 0 1l0 1 l2 8l9 o,sgoio,o, ; ,

THis REPORT Is sueMITTeo PURouANT TO Tut R6ouiReMENTS OF 10 CPR i: < Check oas or more of ,he ,o/,omn#1111) 20.402th) 20 406tel M.73seluHwl 73.71161 30 400teH1H6) 90.3stelHI SO 73teH2Hv) 73.71tel n.) o i 6il = = mHl _

a=wm _

.0.73i iaH iii _ g,EReg,, gg 20.4851eH1Hd61 50.736elGH61 90.73teH2HusedHAl 366A) j 20 eesleH1HN' to.73telGittil 50.734eH2Hv:mHel to 4056sH1Hel 90.731sH2 Hied) to 73telGHal LICINSEE CONT ACT 'OR TMit LEh (121 N.tME TELEPHONE NUMBER ARtaGODt D. N. Morey, General Manager - Nuclear Plant 9 I nis RI o I of I s l 115 tri COMPLITE ONE LINE FOR EACM COMPONENT F AILURE Of 6CRitto IN TMis REPORT n31 MA C. P "" O' +

CAUSE Sv8 TEM COMPONENT C PR S' CAU$t SYSTEM COMPONENT " $'n$,',"$ '

i l I I i l I I I I I I l iI i

! I l l 1 1 I I I I i 1 I I l suPPtnMINTA. REPORT Ex,tCTto n4i MoNTu oar vtaR l E.'M,1'&

] v8: ti,,,, ,o,. surefro suswwCN oAris --"] NO  ;  ;  ; l 1

A T R ACT m ,, ,, , ~ , . . ,0. ,,- . ,, ,, ,,w , n .1 l

I u

At 0722 on 9-20-89, with the unit operating at approximately 61% power, the I reactor was tripped manually following the loss of the operating steam generator i feed pump (SGFP). The 2A SGFP turbine tripped.due to a low auto-stop oil pressure signal. The Shift Supervisor directed a manual reactor trip in order to prevent an unnecessary challenge to the reactor protection system. The unit was stabilized in Mode 3 (Hot Standby).

The lov auto-stop oil signal was caused by the inadvertent opening of the l overspeed trip test valve. Opening this valve lowered auto-stop oil pressure by diverting auto-stop oil to the overspeed test device. Auto-stop oil pressure dropped below the as-found trip set point of the lov auto-stop oil pressure switch causing a SGFP trip. The trip setpoint was fou'id to be higher than it

. should have been.

The unit returned to power operation at 2003 on 9-26-89.

NRC Fe m 386 (6491

[ -e f =.,+ ,

.. .vea.a ...umT .

e . w m .n -

p L ' ' f ? ' ~ LICENSEE EVENT REPORT tLER):

l,UsWMo',fa80,'cCo5'$oti!J%C c "'y ,7.".'"4  ;

TEXT CONTINUATION ,  !?"",7,IMl".^in"oiMf'."dl.'c'S!31f l,".5 08 ' O l

[3/4 0?W,'..=t""se"a'.,'W OF MANAGEMENT AND SUDGETASHINGTON, DC 20603."

l y eaciutv aam m .

oocuT =v . . u , ,,o.,, , ,,, ,,,,,,, }

i' vaan a g,* '  : g,gg i

-  ?

a: _

Farley Nuclear Plant - Unit 2 oisjololol3l6l4 8l9 __

0l1p Q p. 0l 2 or 0 l3 l Tactn . w n.wmcr am wim  ;

Plant and System Identification: 'I Vestinghouse - Pressurized Vater Reactor  :

Energy Industry Identification System codes are identified in the text as '

[XX]. ,

Summary of Event' f

At 0722 on 09-20-89, with the unit' operating at approximately 61% power, the reactor [AB] was tripped manually following the loss of the operating steam ,

-generator feed pump (SCFP) [SJ]. The 2A SGFP turbine tripped due to a low i auto-stop oil pressure signal. .The Shift Supervisor directed a manual reactor trip in order to prevent an unnecessary challenge to the reactor protection system. .The unit was stabilized in Mode 3 (Hot Standby).

Description of Event

(- On 09-20-89, the 2B SGFP had been. removed from service to repair an electro-

!. hydraulic fluid. leak. Therefore, the unit was operating at approximately i

! 61% power. The 2A SGFP vs.s providing feedvater to the steam generators. At *

l. 0722, the 2A SGFP turbine tripped when a worker, who was taking  ;

measurements, inadvertently bumped the overspeed trip test valve lever and '

the valve opened. This lever is in a location that is not easily i

!- accessible. The worker was climbing between the SGFP skid and the:SGFP seal ,;

L piping.

Normally, opening this test valve with the pump in servlee would cause a s pump trip to occur due to the actuation of the overspeed trip device.

However, in this event, the pump tripped on lov auto-stop oil pressure due I to an inoperable overspeed test device. Excessive clearances in the

overspeed test device prevented it from actuating the overspeed trip but caused a drop in auto-stop oil pressure when the test valve was opened. The -

oil pressure dropped below the as-found SGFP trip setpoint of the auto-stop oil pressure switch. During subsequent testing, the setpoint of the -

auto ~stop oil pressure switch was found to be higher than it should have been.

The mechanical overspeed trip for the SGFP was always operable.

Following the trip, the operators implemented FNP-2-EEP-0 (Reactor Trip or Safety Injection) and FNP-2-ESP-0.1 (Reactor Trip Response), ensuring that the unit was safely in Mode 3. The unit was maintained in a stable condition.

- NRC Penn SteA ($49)

.e e u et......ut.10.v

• e c,.ss ow ,

../. uCENSEE EVENT CEPORT (LER) "ll".^.,%',7" J R.Nof,'5a",t'J%'f74' ,T.",,'"'s "

, TEXT CONTINUATWN  !"#,'/,1f.".".'.","31,*A'=f'.%1'!c'.*f,'!# v'".' f#e!TR Urvi.*?%".7Jf"."2S".a,'3t 07 MANAGEwtN1 ANDDVDGE7.VWA HINGTOh. DC 30603 weurv i.aan m acantavata m ua num ia m *A.e m L

e.a ** tP, -"

'#.T; Farley Nuclear Plant - Unit 2 0j5[01010l31614 819 -

0 l1 b -

D lo 0 l1 0F o l1 m, s .w mc w ama nn

[

l Cause of Event This event was caused by personnel error in that an individual inadvertently bumped the overspeed trip test lever causing the valve to open.

Reportability Analysis and Safety Assessment This event is repottable because af the manual actuation of the reactor protection system. After the trip, the following safety systems operated as designed: main feedvater was isolated with flow cor. trol valves and bypass valves closed, auxiliary feedvater pumps started automatically and provided flow to the steam generators, source range 14uclear instrumentation automatically energized, and pressurizer heaters and spray valves operated automatically as required to maintain system pressure. There was no effect l- on the health and safety of the public.

Corrective Action The individual involved in this event has been counseled to be more aware p

of his surroundings and any hazards that may be present when working in tight areas. The overspeed trip test lever has been restrained to prevent inadvertent opening of the valve.

l In addition, the overspeed trip test device has been worked to ensure proper clearance and the setpoint of the auto-stop oil pressure switch has

! been corrected.

1 Additional Information The unit returned to power operation at 2003 on 09-26-89.

No components failed during this event.

This event different vould notconditions.

operating have been more severe if it had occurred under l

senc ewe assa nos

~. . , . . - _ _ - ,,_ _. . _ . _ . . _ _ . _ . .