ML17250B226

LER 90-010-00:on 900609,reactor Trip Occurred from Steam Generator a Low Level Coincident W/Steam Flow/Feed Flow Mismatch.Caused by Faulty Feedwater Flow Controller.Plant Stabilized in Hot shutdown.W/900709 Ltr

ML17250B226
Person / Time
Site:	Ginna
Issue date:	07/09/1990
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 9007170232
Download: ML17250B226 (9)

Text

ACCELERATED DI< RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9007170232 DOC.DATE: 90/07/09 NOTARIZED- NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester AUTH. NAME BACKUS,W.H;

'UTHOR AFFILIATION Rochester Gas & Electric Corp.

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MECREDY,R.C. Rochester Gas & Electric Corp. 05000244'UBJECT:

RECIP-NAME RECIPIENT AFFILIATION LER 90-010-00:on 900609,inadvertent closure of steam generator A causes reactor trip on low steam water level. D DISTRIBUTION CODE: IE22T COPIES RECEIVED LTR ENCL SIZE: S TITLE: 50.73/50.9 Licensee Event Report (LER), Inciden Rpt, etc.

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 PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 D I

INTERNAL: ACNW 2 2 AEOD/DOA 1 1 S AEOD/DSP/TPAB 1 .1 'EOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H 1. 1 NRR/DET/EMEB9H3 1 1.

NRR/DLPQ/LHFB11 1 '1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 = 1 NRR/DST/SICB 7E 1 1 NRR~J3ST- B8 Dl '1 1 NRR/DST/SRXB 8E 1 1 XG FILE 02 1 1 RES/DSIR/EIB 1 1 ILE 01 '1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 . 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 R D

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D NOTE TO ALL "RIDS" RECIPIENTS: ~

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOiVI P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32

/!!Ill!IIIIIIIIIIIII eillilzillv)L'i ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TCLCPHONC ARCA COOC 7I6 546.2700 July 9, 1990 U. S. Nuclear Regulatory Commiss'ion Document Control Desk Washington, DC 20555

Subject:

LER 90-010, 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 is hereby submitted.

This event has in no way affected the public's health and safety.

Ver truly yours, Robert C. Me redy Division Manager Nuclear Production xco U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 9007170232 900709 ADOCK 05000244 POR PDC +~@ g

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LIITAACTl)fovf fo lo00 wo<<. I A. rooforosoNft rff<<oo NotNooofo ftooorffNo oooo) IIU June 1990, at 04ll with the Reactor at approximately full 9,power, On EDST 97~ 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.

The underlying cause of the malfunctioning "A" S/G Feedwater Regulating Valve Control System was a faulty Feedwater Flow Controller. The reason for the fault is undetermined at this time.

Immediate Corrective Action was to stabilize the plant in hot shutdown.

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

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<<LIC fera 5>>EA U.E. IIUCLEAR REOULATORY COMMIESIO<<

(5451 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION r AffROVEO OME ecO 5150MIOc EX>> RIES 'EQI/55 fACILI'TYIIAME I 11 OOCXET IIUMEER IQI LER <<UMEER III ~ AOE 151

~ 50Ucrr TIAL A5 >> I5 Ice rr rr Vre 1 M CA R.E. Ginna Nuclear Power Plant o s o o o 2 449o 0 1 0 0 0 0 6op 06 TEXT Ilf mere <<rec>> re r>>eve>>e! we rrrrrre ~ HRC r

fera ~'el I ITI B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:-'s the root cause of the FC-466A flow controller malfunction is still undetermined, the I&C Shop is continuing to troubleshoot the faulty controller in the I&C Shop.

Any further corrective action will depend upon determinations reached from the above investigation.

VI. 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. Th'e controller's model number is 62H-4E and Serial Number is 2208968.

r PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: The underlying cause of this transi'ent was similar to that for LER 90-007; however, the root cause appears to be. different. 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, and 88-005 were similar events with different root causes.

C. SPECIAL COMMENTS:

None.'1C 1 01M 5>>>>A

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