ML19354E155

LER 89-017-00:on 891218,feedwater Isolation Occurred Due to Erroneous Level Transmitter Root Valve Position Indication. Operations Personnel Reset Feedwater Isolation Signal. W/900117 Ltr

ML19354E155
Person / Time
Site:	Beaver Valley
Issue date:	01/17/1990
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-017-01, LER-89-17-1, ND3MNO:2013, NUDOCS 9001260071
Download: ML19354E155 (4)

Text

~ ~

den

'Af T i.pnone (4tr> 3934aap V8%?4

$hippihDP0't. PA 1$0774004 January 17, 1990 ND3MNO 2013 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 89-017-00 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

In accordance with Appendix A, Beaver Valley Technical Specifications, the following Licensee Event Report is-submitted:

LER 89-017-00, 10 CFR 50.73.a.2.iv, "Feedwater Isolation Due to Erroneous Level Transmittar Root Valve Position Indication".

Very truly yours, T. P. oonan General Manager l Nuclear Operations cj Attachment 9001260071 900117 PDR ADOCK 05000334 i S PDC I i

)

Jcnu2ry 17, 1990

.ND3MNO 2013 Page two cc: Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 C. A. Roteck, Ohio Edison

.Mr. Peter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC- 20555 J. Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector Dave Amerine Centerior Energy 6200 Oak Tree Blvd.

Independence, Ohio 44101 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 G. E. Muckle, Factory Mutual Engineering, Pittsburgh Mr. J. N. Steinmetz, Operating Plant Projects Manager Mid Atlantic Area Westinghouse Electric Corporation Energy Systems Service Division Box 355 Pittsburgh, PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Mr. Richard Janati Department of Environmental Resources P. O. Box 2063 16th Floor, Fulton Building Harrisburg, PA 17120 Director Safety Evaluation & Control Virginia, Electric & Power Co.

P.O. Box 26666 One James River Plaza Richmond, VA 23261 i

i l j

7 eenC'tese age ud NUCLL1A htOphiTDay Comm400$ KIN APPROvt)Otet ho Int 691M LICENSEE EVENT REPORT (LER) 81a* * ' '8' '" r fiCipTV hAMI fil DOCkti NOM $th m FAGE 4 Beaver Valley Power Station. Unit 1 o l5 lo lo lol 3l314 1 lorl 012 tertt i ,

Feedwater Isolation Due to Erroneous Level Transmitter Root Valve Position Indication IVENT DATI Ill Lt h atVMsta tot hEPORT DATI (76 OTHt h 8 ACILITill 6NVOLVED 181 ,

, ,) Wt1 WSN MDNTH D.Y YtAM 78AM $$$4 ,

MONTH DAv ytam f ACM V hawlt N/ A ol6l0l010l l l

~ ~

1l 2 1l8 8 9 d9 0{ 1l 7 0l0 d1 1l7 9l0 N/ A o is so ,o i oi l l ,

SHe alPont is avowritD evaluAN, to tHE a6avialMINn o, to can <e ., .,, m ,inu

" D'

• 3 n ozm ro oii.i x no.13i.H H 7ttim n .o.i.Huoi so mi.im so ni.H H.i n.m.i n0i 010 10 ro aaw. Hum so wi.im n ni.H H.ia

_ g6 gsg., age, n .06te H1H.60 DC.13 e)LtHil 50 73i.H2H.diHAl J66AJ 20 06teH1Hwl St.?SteH2 Hill 60.93i.112 H.6ti He 1 20 0HeH1Hvl 60.796.H2 H1641 to 73(aHilia)

LICIN$$4 CONT Act 90m THis Lim H31 NAVG fittPHONE NUMttR Thomas P. Noonan, General Manager Nuclear Operations ^ * " ' '

4l112 614 131-11 12 1518 COMPLitt ONE LING FOR S ACH COMPON(NT F AILURE DISChlStD IN THi$ REPORT till

" "O *

"$ C CAU58 tv6 TEM COMPON E NT "3 O *HD CAU$4 S v 8 TIM COMPONtNT

" 'f

• DOM R T AbL'$

X JtB RI TIV l K 101815 N l l l l l 1 l 1 l I I I i l i i i i l i I SUPPLEMIN1 AL REPORT E KPECTf D 1141 l MONT H DAY YtAR Sv8Ma$580N

~] =Is i,,,.. . sverno svewss,oh me;

-] No D' " "

• O6i 1l5 9l0 ant.Ac,m,,,,,,.....,..,,,...,,,,.,,..,,,,,,,,,,n.i On 12/18/89, with the Unit in Hot Standby (Operating Mode 3 operations personnel opened the "C" Atmospheric Steam Relie), f Valve to lower the "C" steam generator pressure to facilitate opening of the "C" Main Steam Isolation Valve (MSIV). This is required due to an interlock which prevents the valve from opening on a high differential pressure. Steam Generator level in the "C" Steam Generator (SGC) was indicating 55 percent (%)

on the narrow range scale. Upon opening of the "C" MSIV, at 1323 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.034015e-4 months <br />, steam generator level in SGC swelled to 75% causing

, a Feedwater Isolation FWI) Signal. This caused the closure of the feedwater containme(nt isolation valves. Operations l personnel reset the FWI signal and requested Instrument and Control Following(I&C) a thorough supportanalysis to determine of thethe causethe event of the cause FWI. and corrective actions will be reported in a su,pplemental report.

There were no safety implications due to this event. Feedwater Isolations caused by Hi-Hi Steam Generator Levels are analyzed in Beaver Valley Unit 1 UFSAR section 14.1.9 " Excessive Heat Removal Due to Feedwater System Malfunctions.,"

l

J

1. 1. C 9sem pa U.S EUCLEM $_LIUL& TORY COMMithtold y' ' , UCENSEE EVENT REPORT (LERI TEXT C'!NTINUATION anaoveoouswo sm-e*

tous e num  ;

F ACILITV h4Mt p) DUCkti NOMDth(2) '

LER huMeth 16) PA06 (St n aa ." = ' , t'#,'n Beaver Valley Power Station. Unit 1 0 l5 jo l0 l0 l 3l3 l4 8l9 0l1 l7 Op 0l2 OF smoumnemtman.m. nwwncn.nuwpn 0 l2 )

i DESCRIPTION OF EVENT on 12/18/89, with the Unit in Hot Standby (Operating Mode 3),

operations personnel slowly opened the "C" Atmospheric Steam Relief Valve to lower the "C" steam generator pressure to

! facilitate opening of the "C" Main Steam Isolation Valve l (MSIV). An electrical interlock in the circuit prevents opening '

l l

of the MSIV unless there is less than or equal to five (5) pounds differential pressure across the valve. Steam Generator level in the "C" Steam Generator (SGC) was indicating 55 percent .

(%) on the narrow range scale. Upon opening of the "C" at  !

1323 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.034015e-4 months <br />, steam generator level in SGC swelled to 75%.MSIV,is Th j was sensed by two of three (Channels II and III) narrow range 1 level transmitters causing a Feedwater Isolation (FWI) Signal. l The operators noted that the swell was much larger than i anticipated. The MSIVs were opened on the remaining two J steamlines with a maximum swell of-10% on the narrow range s indication. The FWI signal caused the closure of the feedwater containment isolation valves. Operations personnel reset the l FWI signal and restored the plant to pre-WI conditions. I CAUSE OF THE EVENT An initial analysis determined that the feedwater isolation signal was due to the " swell" phenomena experienced after the  !

opening of the "C" MSIV. Further analysis is being conducted on this event. The results of this analysis will be reported in a supplemental report.

Corrective Actions 5 operations personnel reset the feedwater isolation signal and restored the plant to pre-FWI conditions. Additional corrective actions taken as a result of the analysis of this event will be ,

l reported in a supplemental report. i l

Safety Analysis l There were no safety implications due to this event. The only components at that time to be actuated by the Feedwater i Isolation Sional were the three Feedwater inlet containment.

isolation vaIves to the Steam Generators, which responded  ;

properly Auxiliary (stroked Feedwater closed? to available remained the Feedwater Isolation throughout thissignals.

event.-

Feedwater Isolations due to Hi-Hi Steam Generator Levels are-

-analyzed in Beaver Valley Unit 1 UFSAR section 14.1.9,

" Excessive Heat Removal Due to Feedwater System Malfunctions.

~g,0w . .u.e. v o, m s- m - m a w o