ML18041A188

LER 89-003-00:on 890212,noticed Erratic Operation of Main Feedwater Regulating Valve C & Turbine Trip/Reactor Trip Occurred Due to High Water Level in Steam Generator C.Caused by Valve Vibration & Hydraulic forces.W/890314 Ltr

ML18041A188
Person / Time
Site:	Beaver Valley
Issue date:	03/14/1989
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-003, LER-89-3, ND3SPM:0422, ND3SPM:422, NUDOCS 8903220424
Download: ML18041A188 (14)

Text

ACCELERATED DISIKBUTION DEMONSTRA.TION SYSTEM REGULAT INFORMATION DISTRIBUTION+STEM (RIDE)

ACCESSION NBR:8903220424 DOC.DATE: 89/03/14 NOTARIZED: NO DOCKET FACIL:50-4lg Beaver Valley Power Station, Unit 2, Duquesne Light C 05000412 AUTH. NAME AUTHOR AFFILIATION NOONANFT.P. Duquesne Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 89-003-00:on 890212,reactor tripped due to main feedwater regulating valve failure.W/890314 ltr.

W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR t ENCL I SIZE:

TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:LPDR 2cys Transcripts. LPDR 2cys PDR Documents. 05000412 Application for permit renewal filed.

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-4 LA 1 1 PD1-4 PD 1 1 TAMFP 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRRJ3 /SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 REG Fjj 02 1 1 RES/DSIR/EIB 1 1 RES/DSR/FRAB 1 1 RGN1 FILE 01 1 1 EXTERNAL: EGSG WILLIAMSFS 4 4 FORD BLDG HOYFA 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 ' NSIC MAYSFG 1 1 NSIC MURPHYFG.A 1 1 NOTES: 2 2 NOZE 'IO ALL 'RIDS" RICIPZEPIS:

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 47 ENCL 46

NRC Form 388 U.S. NUCLEAR REGULATORY COMMISSION (9.83)

I( APPROVEO OMB NO. 31504104 LICENSEE EVENT REPORT ILER) EXPIRES: 8/31/88 F AC I LITY N A ME III DOCKET NUMBER (2) PAGE 3/

0 5 0 0 0 1 OF 0 TITLE (4)

Reactor Trip Due to Main Feedwater Regulating Valve Failure FVENT DATE (5) LER NUMBER (5) REPORT DATE I7) OTHER FACILI'TIFS INVOLVED (8)

SEGVENTIAL yh'. REVISION MONTH FACILITYNAMES DOCKET NUMBER(s)

MONTH OAY YEAR YEAR NVMSEA 'Ai NUMBER OAY YEAR 0 5 0 0 0 212 89 89 003 0 0 03 4 89 N/A 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T0 THE REOUIREMENTS OF 10 CFR (I: /Check one or morc OI tnc IoliowrnP/ (11)

OPERATING POWE R

'0.402(bl MODE (SI 20.405(el(I i(i) 20A05(cl 50.35(cl(II 50.73(e) (2)(iv) 50.73( ~ )(2)(v) 73.71(b) 73.71Icl LEYEL (10) P 5 5 20.405(e l(1) (ii) 50.35 Ic I (2) 50,73( ~ ) (21(viil OTHER /Spetiry In AprrreCt

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20.405( ~ l(1) (vl 50.73(e) (2 I (iii) 50.73( ~ )(2)(rrl LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE Mr. Thomas P. Noonan, Plant Manager 41 264 3-1 25 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPORT (13)

MANUFAC. REPORTABLE MANVFAC.

CAUSE SYSTEM COMPONENT p CAUSE SYSTEM COMPONENT TURER TVRER X JB FCV C63 5 Y

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SVPPLEMEN1'AL REPORT EXPECTFD (14) MONTH OAY YEAR EXPECTED SU 8 M I SS I 0N DATE (15I YES //I ycr, comp/etc EXPECTED SU84IISSIOIY DATE/

ABSTRACT ILimrt to /400 rpeccr. /c,, epprovimeteiy /i/teen r/nple torte tyPcwrinen /inn/ l(d)

On 2/12/89, with the Unit in Power Operation, a power reduction from 904 reactor power to 50% reactor power was in progress as part of End of Core Life programs. At 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, operators noticed erratic operation of the "C" Main Feedwater Regulating Valve (MFRV). The operators placed the "C" MFRV in manual to control steam generator level. At 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> at approximately 55~ reactor power, the "A" Main Feedwater Pump was shutdown to reduce the pressure differential across the valve allowing easier valve movement and control. At 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, a turbine trip/reactor trip occurred due to a high water level in the "C" steam generator. The operators stabilized the plant in Hot Shutdown utilizing the Emergency Operating Procedures. The HC" MFRV was found to have sheared anti-rotation pins and the stem detached from the valve plug. The cause for the valve failure was attributed to hydraulic forces and vibration acting over time. The MFRVs were all disassembled, inspected and repaired as necessary. This event was reported to the Nuclear Regulatory Commission at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, in accordance with 10CFR50.72.b.2.ii.

There were no safety implications to the public as a result of this event. This type of event has previously been analyzed as stated in the Updated Final Safety Analysis Report, Section 15.1.2, "Feedwater System Malfunctions Causing an Increase In Feedwater Flow".

8903220424 8903i4 $)

NRC Form 358 PDR ADOCK 05000412 (9 83) S PNU

NRC Form 3SSA U.S. NUCLEAR RFOULATORY COMMISSION (943)

LICENSEE E ENT REPORT ILER) TEXT CONTINUATION APPROVED OMB NO. 3150-CI04 EXPIRES: 8/3)/88 FACILITY NAME <>co /r roqo/rod. o>> odd/I/orM/HRC Form36548l <<7)

DESCRIPTION On 2/12/89, with the Unit in Power Operation (Operating Mode 1),

Operations personnel were reducing reactor power from 90% to 50<

as part of End of Core Life programs. Prior to the Operating crew assuming the shift at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 2/11/89, the <<B<< Main Feedwater Regulating Valve (MFRV) had previously exhibited erratic valve control for steam generator water level. The <<B<<

MFRV was in the automatic mode, however, the valve was not controlling smoothly. At 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, operators noticed erratic operation of the <<C<< MFRV. At 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br />, at approximately 554 power, the <<A<< Main Feedwater Pump was shutdown. At 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, the water level in the <<C<< steam generator increased to the high-high level setpoint (75%) causing. a turbine trip and feedwater isolation signal. The turbine trip caused a reactor trip, since reactor power was above the trip permissive of 49'.

The feedwater isolation signal caused the following actions to occur: 1) trip of the running main feedwater pump, 2) auto-start of the auxiliary feedwater pumps, and 3) closure of the main feedwater regulating valves and bypass valves.

Following the reactor trip, the operators utilized the Emergency Operating Procedures (E-0 "Reactor Trip or Safety Injection<< and ES-0.1 "Reactor Trip Response" ) to stabilize the plant in Hot Standby (Operating Mode 3).

APPARENT CAUSE OF THE EVENT The cause for this event was attributed to the failure of the

<<C<< Main. Feedwater Regulating Valve (2FHS*FCV498). This valve is a Copes-Vulcan, Model No. D-100-160, Part No. 16-FA37RG. The valve failure was attributed to the hydraulic forces and vibration, which over time, mechanically excite the valve, damaging the anti-rotation cage slots, plug guides, retaining pins and valve stem. The <<B<< Main Feedwater Regulating Valve was found to have damaged anti-rotation pins.

Nr)C FORM 300A 'U.S ~ CPCI )988-33<' )09 000)0 IS 83)

NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION 194)3)

LICENSEE ENT REPORT (LERI TEXT CONTINUA ON APPROVED OMB NO. 3160&)04 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL +"'2 REVISION NVM8ER ):. 1 NUMSSR spinto Beaver Valley Power Station, Unit 2 o s o o o 4 1 2 8 9 0 0 3 0 0 03oF 0 4 TEXT /lfmoro /4 rtr)o/rod, oto tddr)/ono/IVRC Form 3664'4/ OS)

CORRECTIVE ACTIONS The following corrective actions were taken as a result of this event:

Immediate:

1). Operations personnel utilized the Emergency Operating Procedures to stabilize the plant in Hot Standby.

2). The main feedwater regulating valves were disassembled and inspected. The anti-rotation pins were replaced on all main feedwater regulating valves.

Long-term:

An Engineering Memorandum has been generated requesting Engineering to identify an actuator and valve design which will eliminate the main feedwater regulating valve problems due to the hydraulic forces and vibration which over time, progressively damage the valves.

2). All three steam generators will be inspected during the First Refueling Outage for potent'ial loose objects.

SAFETY IMPLICATIONS There were no safety implications to the public as a result of this event. This type of event has previously been analyzed as stated in the Updated Final Safety Analysis Report (UFSAR),

Section 15.1.2, "Feedwater System Malfunctions Causing an Increase in Feedwater Flow". Additionally, all the required Engineered Safety Features (ESF) system components actuated as follows as a result of the steam generator high-high water level condition 1). Turbine trip, causing a reactor trip because reactor power was greater than the P-9 trip permissive, 2). Feedwater Isolation (FWI) signal, causing the following:

A). Trip of the running main feedwater pump, B). Automatic start of the auxiliary feedwater pumps 2FWE*P22, 23A and 23B),

C). Closure of the main feedwater regulating valves and bypass valves.

NRC FORM 34OA ~ V.S. CPOI )988-920-889 ~ OOOTO (94)3)

NRC Form 388A V.S. NUCLEAR REGULATORY COMMISSION (94)3)

LICENSEE ENT REPORT ILER) TEXT CONTINUA ON APPROVED OMB NO. 3)50&)04 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3)

SEOUENTIAL PP?r REvrsKIN YEAR gg NUMBER .Rrr. NUMBER 8eaver gal le Power Station, Unit 2 o s o o o 4 1 2 8 9 003 0 0 0 4 OF 0 4 TEXT IIImoro Z>>oo /4 re/rr/rod, Iroo EdcNane/HRC %%dmr 3684 9/ lll)

In addition, the Nuclear Steam System Supplier (NSSS) has evaluated the utility's engineering interpretation of the Steam Generator Parametric Loose Object Licensing Report (WCAP-12101),

which addressed the safety significance of the potential loose part (anti-rotation pin from 2FWS*FCV498) which could be trapped in the "C" steam generator tubesheet annulus. It was concluded that the estimated time required for the loose object to wear into a tube to the minimum allowable wall thickness, is 2.4 years. The NSSS concurred with this safety evaluation justifying continued operation of the remaining operating cycle.

REPORTABI LITY This event was reported to the Nuclear Regulatory Commission at 0300 hours in accordance with 10CFR50.72.b.2.ii. This written report is being provided in accordance with 10CFR50.73.a.2.iv, as an event involving a reactor protection system (RPS) or engineered safety fea'tures (ESF) system actuation.

PREVIOUS OCCURRENCES There have been no previous Licensee Event Reports issued on this type of event/equipment failure at Beaver Valley Power Station Unit 2.

NRC FORM 388A AU.S. GPOr IOSS SSB SSP I)0r)10 l94)3)

gled~

Duquesne Nuclear Group lt TelephOne (412) 393-6000 P,O, Box 4 Shippingporh PA 15077~

March 14, 1989 ND3SPM:0422 Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 LER 89-003-00 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 89-003-00, 10 CFR 50.73 a.2.iv, "Reactor Trip Due to Main Feedwater Regulating Valve Failure".

Very truly yours, T. P. Noonan Plant Manager vhy Attachment

March 14, 1989 ND3SPM'0422 Page two CC: Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Rd.

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 Mr. Alex Timme, CAPCO Nuclear Projects Coordinator Toledo Edison 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 6 Power Co.

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

,/