ML17262A437

LER 90-010-01:on 900609,reactor Trip Occurred from Steam Generator a Low Level Coincident W/Steam Flow/Feed Flow Mismatch.Caused by Faulty Feedwater Flow Controller. Controller replaced.W/910409 Ltr

ML17262A437
Person / Time
Site:	Ginna
Issue date:	04/09/1991
From:	Backus W, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-010, LER-90-10, NUDOCS 9104190352
Download: ML17262A437 (16)

Text

ACCELERATED DIURIBUTION DEMONSTTION SYSTEM REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)

ACCESSION NBR:9104190352 DOC.DATE: 91/04/09 NOTARIZED: NO DOCKET I FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester 05000244 AUTH. NAME BACKUS,W.H.

'UTHOR AFFILXATION Rochester, Gas & Electric Corp.

G MECREDY,R.C. Rochester. Gas & Electric Corp.

RECIP.NAME RECXPIENT AFFILIATION

SUBJECT:

LER 90-010-01:on 900609,reactor trip occurred from "A" steam generator caused by inadvertent closure. Caused by controller malfunction;Plant stabilize in hot shutdown & change out D existing controller w/spare.W/910409 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR / ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Tncident Rpt,, etc. J SIZE:

NOTES:License Exp date in, accordance with 10CFR2,2.109(9/19/72). 05000244 A RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 v' AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1

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PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATI'OURNAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

PULL TEXT CONUERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

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,ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER N. Y. 14649.0001 ROBERT C MECREDY TELEPHONE Vis> P//.sident AREA CODE 716 546 2700 C/nna NudcA/ P/odu/s/on April 9, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington,. DC 20555

Subject:

LER 90-010 (Revision 1), Inadvertent Closure of "A" Steam Generator Main Feedwater Regulating Valve Due to Controller Malfunction Causes a Reactor Trip On Low Steam Generator Water Level R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF) including the Reactor Protec-tion System (RPS)", the attached Licensee Event Report LER 90-010 (Revision 1) is hereby submitted. This revision is necessary to revise Section III (Cause of Event) due to the root cause being identified.

Very, truly yours, Robert C. Mecred Xco U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 920415>0.52 %F0409 PDR ADOCK 05000244 S PDR

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"B JBLC F18 0 Y 9,r. v IUttLININTALIltOAf tttlCTIO IIAI aeONTN CAY TtAR tttICTIO WININION OATI I'I ~ I Tlt IIItee. e<<e>>re>> lltlCTlO IUINIIWONOA tll NO aAITAAcT Iarwvl N I col eeee<<. I e., ettreerrr>>Nrt INN<<e Netreeteee Itteerrrt>>e er>>U IIII June 1990, at 0411 EDST with the Reactor at approximately 974'ull 9,power, On a reactor trip occurred from "A" Steam Generator (S/G) Low Level coincident with "A" S/G Steam Flow/Feed Flow mismatch.

The two reactor trip breakers opened as required and all shutdown and control rods inserted as designed.

The reactor trip was due to a malfunctioning "A" S/G Main Feedwater Regulating Valve Control System. r The underlying cause of the malfunctioning "A" S/G Feedwater Regulating Valve Control System was a faulty Feedwater Flow .

Controller. The failure of the controller was localized to a 4 Stage AC Amplifier section.

Immediate Corrective Action was to stabilize the plant in shutdown.

'ot Subsequent action was to change out the existing controller with a spare.

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L'ICENSEE EVENT REPORT (LER) TEXT CONTINUATION ASSROV EO OME HO $ 1$ 0&104 Exf IREE. SIEIIE$

fACILITYHAMS III OOCKET HUMEER Ill LER HUMEER IEI SAOE IEI 5EOVENTIAL NEVr5 ION NVM EN M IA R.E. Ginna Nuclear Power Plant o 5 o o o2 44 9 0 010 1 0 4 OF 0 6 TEXT N moro Moco <<roRNod. vm rrrrorm<<<<IIC form ~'Il I ITI G. SAFETY SYSTEM RESPONSE:

None III'AUSE OF EVENT A. IMMEDIATE CAUSE:

The reactor trip occurred due to "A" S/G Low Level

< 304, coincident with "A" S/G SF/FF mismatch

> O.BE6 lbm/hr.

B. INTERMEDIATE CAUSES:

The "A" S/G Low Level coincident with "A" S/G SF/FF mismatch was due to the "A" S/G Main Feedwater Regulating Valve inadvertently closing.

The "A" S/G Main Feedwater Regulating Valve inadvertently closing was due to its Foxboro Model 62H Controller (i. e. FC-466A) mal functioning. FC-466A cur'rent output failed low. Failure low of the output c,"".".ent immediately- causes the feedwater valve to close.

C. ROOT CAUSE:

The underlying cause of FC-466A output current failing low was the degradation of the, first stage transistor in FC-466A's 4 Stage AC Amplifier. This failure was due to the change in the transistor's gain characteristics.

IVo ANALYSIS OF EVENT This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires reporting of "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)," in that the "A" S/G Low Level coincident with "A" S/G SF/FF mismatch reactor trip was an automatic actuation of the RPS.

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NIIC Sons 35EA U.E. NUCLEAII IIEOULATOIIYCOMMIEEION o <0431 LICENSEE EVENT REPORT {LER) TEXT CONTINUATION ASSROYEO OME NO I 3/50&105 E)ISIAES EI31/$ 5 SACILITY NAME 111 OOCKET NUMEEII (21 LEII NUMEEII (EI SAOE I31 VEAII 55OV5NTIAL sovlslon nVM 5A nvM os R.E. Ginna Nuclear Power Plant o 5 o o o2 449 0 0 1 0 010 6 OF 06 TU(T IIISSOO MO>> A>>OVnd, O>> OOWOOW IYIC A<<SI AM52 I ITI B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

FCC-466A was tagged on January 25, 1991 to be discarded after the 1991 outage when the Advanced Digital Feedwater Control System is installed.

VIo ADDITIONAL INFORMATION A. FAILED COMPONENTS:

The failed component was, the "A" S/G Main Feedwater Regulating Valve Controller FC-466A. This controller was manufactured by Foxboro Company. 'he controller's model number is 62H-4E and Serial Number is 2208968.

B. PREVIOUS L"..Rs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: No other documentation of similar LER events with the same root cause at Ginna Station could be identified. However, LERs85-006, 85-019,88-003, 88-005, and 90-007 were similar events with different root causes.

C. SPECIAL COMMENTS:

None.

NAC SOIIM 3ooA

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