ML17262A434

LER 91-002-00:on 910304,loss of Offsite Power Circuit 751 Occurred Due to Ice Storm,Resulting in Automatic Actuation of EDG & Turbine Runback.Buses Restored to Normal Power & EDG realigned.W/910402 Ltr

ML17262A434
Person / Time
Site:	Ginna
Issue date:	04/02/1991
From:	Backus W, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-002, LER-91-2, NUDOCS 9104100183
Download: ML17262A434 (22)

Text

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ACCELERATED Df'RIBUTION DEMONS'ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9104100183 DOC.DATE: 91/04/02 NOTARIZED: NO DOCKET 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. Baltimore Gas & Electric Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 91-002-00:on- 910304,turbine runback occurred '& "A" emergency diesel generator started & tied into safeguard buses. Caused by loss of power to safeguards buses & ice D ltr.

storm.Restore'd power to safeguards.W/910402 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR JI ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

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NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 A, RECIPIENT COPIES RECIPIENT COPIES D,

ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A' 1 1 S

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D NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOiVI P l-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 31 ENCL 31

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I ~ I AI ~ P iic p 4 / 'coen 51A'cc ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 RQBERTr, MECREDV TELEPHONE Vice Piesidenc AREA COOE 7]6 54S 2700 pinna e4u<lear P<oduclion April 2, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 91-002, Loss of Offsite Power Circuit 751, Due To Ice Storm, Causes Automatic Actuation of the ESF and RPS, (i.e. Emergency Diesel Generator Operation and Turbine Runback)

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 Protection System (RPS)", the attached Licensee Event Report LER 91-002 is hereby submitted.

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

Ve truly yours',

Robert C. Me red xcp U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 9104100l83 9i0402 PDR ADOCK P'llew'&8

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HAC teeee SSS t$ 451 vf, eAcLKAA AIOULATDATcoeNIAKw AeeAOYID OMI NO.IIK0 Olov UCENSEE EVENT REPORT LER) IXSIAII 0/II/IS YACI LITT HAMI Ill DOCXIT NVMSIA Ql R.E. Ginna Nuclear Power Plant o 6 o'o o 244 1Qf 09

'" Loss of Offsite Power Circuit 751, Due To Ice Storm, Causes Automatic Actuation of the ESF and RPS i.e. Emer enc Diesel Generator ration and in back IVIIITDATI ISI LIA NLAelt1 ISI AKYOATOATt Ih OTHIA SACILITIIS INVOLVI0 Nl MD>>Tee OAY YIAA YIAA ll4VI>>tt>>l eel VAe4ee OAY YIAA ~ AOLITT NAMLS OOCAIT NVMSKAISI HVeeetA eeeeeee e A MONTH 0 5 0 0 0 0 3 4919 002 0 0 0 4 02 91 0 6 0 0 0 Oel AATINO THIS 1IPOAT IS SUSMITTID YVIQUANTT 0 THI AIOvlltMlltTIOe I I 45 1 $ : Iceeeee eee ee eeeee et tee ~ eeeeett Illl MOOS Ill Tt.eSI le) M.TSNI Q I llel TL7141 eOtt I 1 SS.eOI 4 Ill III MMlellll M.TSNI Q I lel TS.TI 41 LtvIL 0 9 7 SSAS4lllllll , MMNIQI M.TSlelNllell DTNI1 Iteeette M Aeeeeet we>> eeet M TeeL>>JIC /eeet 50.eM 4 I II I IMI M.TS4lalll M.5SMIQIIHIAIAI JISM 50ASI 41111 lie 1 M.TI41N II II M.TSNNKlleMINI 50ACS 41 Illltl M.TI 41NI I XO M.T54IQIlel LICSNSK ~ CONTACT SOA TNII LIA lltl HAMI TILIYHONINVMltA Wesley H. Backus AAIACOOK Technical Assistant to the rations Mana er 3 1 5 5 2 '4 - 4 4 4 6 COMtLITI ONI LINI t01 tACH COMYOIIINT >AILVAIDKICAISIDIN THIS 1SSOAT IIII CA VSt SYSTIM COMtONINT MA>>VXAC TVAIA

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TO NtAOI <Pj'.'ja5j~ CAVSI SYITIM coMeoNINT MANUSAC TUN IA leOATAS L TO NYAOI 4.4.-.~~%4

~'Vwe+7:Pg'VYYLKMINTAL AKYOAT IXtlCTIO lleI MONTH CAY 'YIAA IXIICTID LVIMISSION OATS 11 ~ I Y I I lit tee. teeee>>M tXAtCTIO SV5 MISSIO>> OATtl NO AJST AAcT ILJevt te le44 eeet>>. I A. eAeeeeeeee>>t t>>>>ee e>>teeeeeee ttteeetetteee eeeeel IIII On March 4, 1991 at 0148 EST, with the reactor at approximately 97% full power and again on March 7, 1991 at 0248 ESTY with the reactor at approximately 80% full power, a turbine runback occurred and the "A" Emergency Diesel Generator started and tied into safeguard buses 14 and 18. \

The Control Room operators performed the appropriate actions "A" of AP-TURB.2 (Automatic Turbine Runback) and verified that the Emergency Diesel Generator was operating properly and that safeguards buses 14 and 18 were energized. The plant was sub-sequently stabilized at, approximately 20% full power less than when the events started.

The cause of the events was the loss of power to safeguards buses 14 and 18 due to loss of offsite power 34.5 KV circuit 751.

Circuit 751 was lost due to RG&E system disturbances caused by a major ice storm.

Corrective action was to restore normal power "A" to safeguards buses 14 and 18 from offsite power and to stop the Emergency Diesel Generator and realign it for auto standby.

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Hllc ewe AOA V.S. HVCLSAA 1tOVLATOAYCONN~OH IS4SI LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AeeAOYSO OMt HO SI SOWIOe r

tAelASS HANt lll t/SI/SSACILITY OOCAST HVNttA 111 LIA HVNttA Itl eAOt ISI SSOVSHTIAL YQIOM H M 1 A R.E. Ginna Nuclear Power Plant 0 5 0 0 0 2 4 4 91 002 0 0 080F 0 9 TtxT llleeee HNee H teereec eee eeeeeeel HAc ANe Ie'il ITl I

C. ROOT CAUSE:

The underlying cause of the loss of offsite power 34.5 KV circuit 751 was RG&E system disturbance due to the effects of a major ice storm.

ANALYS1S OP EVENT The events are 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 automatic turbine runback was an automatic actuation of the RPS and the starting of the "A" Emergency Diesel Generator was an automatic actuation of an ESF system.

An assessment was performed considering both the safety consequences and implications of these events with the following results and conclusions:

o All reactor control and protection systems performed as designed thus limiting the overall effects of the turbine runback transient.

o The "A" Emergency Diesel Generator operated as designed by starting and supplying emergency power to safeguards buses 14 and 18.

Offsite power 34.5 KV circuit 767 operation supplying power to the "B" train safeguards was still in buses and subsequently was lined up to sunnily power to the "A" train safeguards hue"s.

Based on the above, it h'ealth and safety was assured at all times.

can be concluded that the public's

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