ML17262A419

LER 91-001-00:on 910215,loss of Safeguards Bus Occurred During Emergency Diesel Generator Monthly Load Test.Caused by Supply Breakers Tripping.Bus 18,emergency Diesel Generator 1A & Output Breaker inspected.W/910318 Ltr

ML17262A419
Person / Time
Site:	Ginna
Issue date:	03/18/1991
From:	BACKUS W H, MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-001, LER-91-1, NUDOCS 9103260186
Download: ML17262A419 (22)

Text

ACCELERATED DILUTION DEMONSTP+TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9103260186 DOC.DATE: 91/03/18 NOTARIZED:

NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION BACKUS,W.H.

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

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 91-001-00:on 910215,loss of safeguards bus during Emergency Diesel Generator monthly load test.Caused by supply breakers tripping.Bus 18,emergency diesel generator 1A&output breaker inspected.W/910318 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: 0 TITLE: 50.73/50.9 Licensee Event Report (LER), nciden Rpt, etc.NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

D 05000244 D RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D N SPLB8D1 02 GN1 FILE 01 EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC MURPHYiG~A COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DS P NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EIB I L ST LOBBY WARD NSIC MAYS,G NUDOCS FULL TXT COPIES , LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 D D NOTE TO ALL"RIDS" RECIPIENTS:

D D PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 E 1

'iI//'ni j/!ri/r ROCHESTER GAS AND ELECTRIC CORPORATION rr t w ll (lall~+~/'t rorrt stntc~89 EAST AVENUE, ROCHESTER N.Y.14649-0001 ROBERT C.MECREDY Vice President Cinne Nucteer Production TEt.EPHOirK AAEA CDOe P te 546 27M March 18, 1991 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 91-001, Loss of Safeguards Bus During Emergency Diesel Generator Monthly Load Test, Due To Supply Breakers Tripping, Causes A Condition Prohibited By The Plant Technical Specifications R.E.Ginna Nuclear Power Plant Docket No.50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B), which requires a report of,"any operation'rohibited by the Plant's Technical Specifications", the attached Licensee Event Report LER 91-001 is hereby submitted.

T his event has in no way affected the public's health and safety.Ve truly yours, Robert C.M cred XC;U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 9l03260i86 9103iS PDR ADOCK 0 000244~\PDR k

HAC Ssrrs SSS)$05)LICENSEE EVENT REPORT (LERl UA NVCLSAA ASOULAT01'0 COSWSWKNI AsrHOYSO Ossl HO.SISS.0)Ov~SSIACS SSSI/SS DocAST HVMSSN Ql SACIL)TY HAS)0 Ii)R.E.Ginna Nuclear Power Plant o 6 o o o 244 IOF0 g'" Loss of Safeguards Bus During Emergencv Diesel Generator Monthly Load Tests Due To Su 1 Breakers Tri in, Causes A Condition Prohibited B The P1ant Tech S cs.CVlNT OATS ISI MONTH DAY YCA1 LC1 NVssll1 lll 1lso1T D*TC Ill OTHl1 SACILI'T)ll INVOLVCO W)021 91 MSAAT)HO N MOOS ie)SOW C1 LtvlL 0 9 YCA1%'toulrsr<AL Huvslr ssuMS~1 MOHTH OAY YCA1 SACsLstr HAsSIS OO<<ST HVMSSAISI osooo 001 0o3189 5551)SI TS.TI III~0.T 54 I Q)or I SC.TS4)QI)rl N.T 5 lsl Q I)rll SC,T 5 4)Q)irW)IAI~0.5 54)it)lrWI I~I l0.154)QUsl tl.sNlsl N JNs)III SCMHIQI 50.sot)i)SILAN 4)I)I IS 50 ACS Is)I I I Ill 50AOS 4 I I I I I W I SCA)>>41(1) lsrl SO.SN)s I I)I lrl o 6o oo 0TH C1 ltsssrrs 4 Asrssrr srsr ss0 ls TssL HAC Ssrrr 550A)~0.T 54)Q))0~0T 5 4)Q)Ill lO.T 5 4 I Q I I Wl L)CCHSll CONTACT S01 TH)S LC1 l)tl TH)s Acso1T ll svsMITTSD svAsuAHT To THc Atov)ASMCNTT 0s)lcs1$s lorrs sss<<sssrs sr srs rsrrrrrs)IIII HAMS Wesley H.Backus Technical Assistant to the ation Ma TCLCSHOHC NVMSCII A)ISA COOS 31 5524-444.6 COSSSLSTt ONC LINC SOA CACN COMSOHCNT SAILU1C OCSC1)SCD SN TH>>CtSO1T I)t)CAVSS SYSTCM COSSSOHCNT MAHVSAC TVWC1 CSOSITASLC To HSIOS SYSTCM COMSOHCNT MAHVSAC TVAC1 CSOSITASL To HSWDS SVSSLtMlHT*L AtSOAT lSSlCTCO I)sl MOHTH CAY Y CA)I CXSCCTCO LVSM<SSIOH DATC 11~I YCS OS rsr.rrrusrH 55SCCTCO SVSM)55)0>>

OATS)HO ASSTAADT IL4srr ss Iso)ssrr>>.Ss., sssrssssrsNrs HINrrs r4srrsssrr lrsrsrsrHs Mrssl ll~I.-I February 15, 1991 at 0845 EST with the reactor at approximately

.74 full power, the emergency and normal feed breakers to Bus 18.ripped while the 1A Emergency Diesel Generator was being paral-eled onto the bus.The loss of Bus 18 placed the plant in a condition prohibited by plant Technical Specifications.'mmediate operator action consisted of starting an additional service water pump from Bus 17.Subsequently, the Control Room operators declared an Unusual Event: and commenced a plant shutdown to comply with plant Technical Specifications.

The underlying cause of the event is undct.ermined at this time.Further testing and evaluation will be performed.

Corrective action was to inspect Bus 18, the 1A Emergency Diesel Generator output breaker and the 1A Emergency Diesel Generator.

Components were found satisfactory and returned to service.sr1C Ssrrs SN)SASI I

~~~~~I I~l'I I I I I~I~I~~~~~~~~~~II II~~~~~~~~I~~~~~J g~I~~~~I~~~~~~~~I~~~~~~~~I I~~~~~I~~~~-~~II~~II~~~~I I II~~~~~~II~~~~II II I~~I~~'~~~~II 0

~~~~I I I I'I I I 0 I~~~~e~~~I~~~~~~~~~II~~~~~~II~~~~~~I~~I~~~~~I~~~~~~0~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-~~~II~~~~~~~~~

~~~~0 I I iI I I I~~I~I~~~~-~~~~~~-~~~~~~Ql~~'I'I'~~~~~I 8~~I~'IA'A~~I~~I GI~~~~I I~I~~~<Q~I I~~~~II~~~~'~~II~~~~II I~~QI~~~

0

~~~I~~~~~~~~I~~~~I~I~~~~~~~s~~~~~~~~~~~I~~II~~~~~~~~~~~~~~~~~~~~~~I~~I~~~~II~~~~~~~

~~~~~~~II~~~I~~~~~~s~~~~~~s~~~~~~~~~~~~s~~~~~~~~~~~~s~~~~~~~~~~~~~~~I~GI~~~~Q~~~~s~~~~~~~~~~~~II~s~~~~~~~~I~~

0 II lit hg II i

~~~~II~~I~I~~~II~~~~~~~~~~~~~~~~~~~~~e~~~s o~-~~~~~~~~~0~~~~~~~~~~~~~~~II~~~~~~~~~II~~~

~~~~~'~I I I I I~~I~~~~~~~0 0~~-~~~~~~~~~~~~~~~I~I~~~-~s~~I~I~e~~~~~II~~~~~~~~~~~~~II~~~~~~~~~~I~~~o II~~~~~~~

1I P IC NIIC fons$NA IMJ I LICENSEE EVENT REPORT (LER)TEXT CONTINUATION Il.$.NUCLlAII AtOULATOIIY COMMI$$ION/Aff<<OVTO OUI NO gl$0&IO$4)CttAIS$/31+$fACILITY NAM$III OOC<<tT NUMICII IXI LIII NUMIl1 III$$Q<<$<<TIAL~IVY 1 II$VISIOH H M~8~AQK III R.E.Ginna Nuclear Power Plant TEXT IN oaf<<MCe<<~.vm<<<<M$MW lYIIC A$<<<<~lI II'o s o o o 4491-00 1-009 or 09 , B.ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE.

In addition to the actions taken to return the systems to normal status, the following action will'be taken: o Additional testing and calibration of.the 50G overcurrent ground relay for Bus 18.0 0 Paralleling the 1A Emergency Diesel Generator to Bus 18 per PT-12.1 has been performed twice while being monitored with extensive instrumenta'-

tion.The immediate results identified that breaker speed of closure and operator synchroni-zation is functioning correctly.

The results of this effort will be further evaluated by the Electrical Engineering Department.

Applicable procedures for paralleling the Diesel Generator are being revised as required to be consistent with training.VI.ADDITIONAL INFORMATION A.FAILED COMPONENTS:

None.B PREVIOUS LERs ON SIMILAR EVENTS: A similar LER event historical search was conducted with the following results.No documentation of similar LER events at Ginna could be identified.

C.SPECIAL COMMENTS: None.N<<C fOAU$$$A iOA$~