ML17262A291

LER 90-016-00:on 901212,reactor Trip Occurred from Inadvertent Intermediate Range Trip.Caused by de- Energization of One Out of Two Intermediate Range Nuclear Instrument Sys High Flux Trip bistable.W/910111 Ltr

ML17262A291
Person / Time
Site:	Ginna
Issue date:	01/11/1991
From:	Backus W, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-016, LER-90-16, NUDOCS 9101160176
Download: ML17262A291 (9)

Text

ACC.'LILERATL'D D!c~RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9101160176 DOC.DATE: 91/Ol/11 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. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

LER 90-016-00:on 901212,reactor trip inadvertent intermediate range trip. Caused by de-occurred from energization of one out two intermediate range nuclear D instrument sys high flux trip bistable.W/910111 ltr.

S DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

ENCL 2 SIZE:

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)ie 05000244 A s

,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 1 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' NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST SPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 R ..1 1 RES/DSIR/EIB 1 1 RG 1 1 1 EXTERNAL EG&G BRYCE E J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 ) NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE O'ASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. -"0079) TO ELIMINATEYOUR NAiv1E FROil'I DISTRIBUTION I ISTS FOR DOCUXIENTS YOU DON'7 NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

~p ROCHESTER GAS AND ELECTRlC CORPORATION + 89 EAST AVENUE, ROCHESTER N.Y. 1464&-000'f PU'l>tP<1 k Mfk l l/', Tkkr',v'i'REA W<<e l'gt e COD%V>t 546 27CO Ctlf1 '4 0 I, d January 11, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 90-03.6, . Inadvertent Intermediate Range Trip During Transfer of 480 Volt Bus 14 to the "A" Emergency Dies'el Generator Causes a Reactor Trip R.E. Ginna Nuclear Power Plant Docket No. 50-244

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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 90-016 is hereby submitted.

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

Very truly yours, Robert C. Ntu:red//

xc: U.S. Nuclear Regulatory Commission Region I 475. Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector

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NAC torm SSSA V.S. HVCLSAII IISOVLATOIIYCOMMISSION I9451 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION /

AttROVSO OMS HO 5ISO&105 SNSINas. SnIISs t I LITT HAM9 AC III OOCKST NVMSKII ITI LSN NVMSS1 IS) ~ ACS ISI 5 5 0 V5 H 5 I AL 15VI$ IOH HVM HVM SA R.E. Ginna Nuclear Power Plant 0 5 0 0 I 0"f 2 4 4 9 Q 0 1 6 QIOQ20FQ 7 TG(T IN mort tooot N rtsvvto. vto oornoootr wIC Arm ~'tl IITI PRE-EVENT PLANT CONDITIONS The plant was in the process of starting up subsequent to the plant trip of 12/ll/90 (discussed in LER 90-013). The reactor was at approximately 3% full power awaiting clearance that secondary chemistry parameters were within specification.

The Control Room operators'ere in the process o'f transferring Bus 14 from its normal power supply to the "A" Emergency Diesel Generator as part of the repair procedure for the Bus 14 Undervoltage Monitoring System.

The Bus 14 Undervoltage Monitoring System Event'is discussed in LER 90-015.

DESCR1PTION OF EVENT A. DATES AND APPROXIMATE TIMES OF MAZOR OCCURRENCES:

December 12, 1990, 2322 EST: Event Date and Time 0 December 12, 1990, 2322 EST: Discovery Date and Time December 12, 1990, 2322 EST: Control Room operators verify both Reactor Trip Breakers open and all Control and Shutdown Rods inserted.

December 12, 1990, 2327 EST: Control Room operators close both Main Steam Isolation Valves (MSIVs) to terminate plant, cooldown.

0 December 12, 1990, 2332 EST: Plant stabilized at hot shutdown.

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On December 12, 1990, at approximately,2322 EST, with the reactor at approximately 34 full power,. the operators were transferring power supplies for Bus 14, per the direction of procedure M-48.14 (Isolation of Bus 14 Undervoltage System for Maintenance, Troubleshooting, Rework and Test). During this transfer, a momentary loss of power occurs to Bus 14.

Bus 14 feeds MCC-1C, which feeds Instrument Bus 1B.

'herefore, Instrument Bus 1B had a momentary loss of power, which de-energized the bistable for Intermediate Range (IR) Nuclear Instrument System (NIS) Hi,gh Flux Trip, for IR NIS Channel N-36. This reactor trip was due to one (1) out of two (2) IR NIS High Flux Trip bistables becoming de-energized.

The Control Room operators immediately performed the applicable actions of Emergency Operating procedures E-0 (Reactor Trip Or Safety Injection) and ES-0.1 (Reactor Trip Response) and stabilized the plant in hot shutdown. Subsequently, the MSIVs were closed to terminate a plant cooldown.

The Control Room operators notified higher supervision and the Nuclear Regulatory Commission (NRC) of the reactor trip.

C. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:

None.

D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

None.

E. METHOD OF DISCOVERY The event was immediately apparent due to alarms and indications in the Control Room.

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~A US HUCLCAA AICULAIQAYCOMM>SSIOH LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AeeAOYCO Oud sO 9150 OI04 CeelRCS dgI CS SACILITY IIAMC lll OOCXCT IIUMCC II 'CI LCII HVMCC II ICI ~ ACC 151 SCQUShe<AL eSS'5 CH 4Uv Cw RUMSI e R.E. Ginna Nuclear Power Plant 0 /GIORNO(0(2(4 4 9l0 Otl G 0I 0 0(50F0 7 TEXT llfmme leeee H revved, we eeeelemM HAC Porn PC@'el 1111 accomplish this load transfer presents a probability of a reactor trip (if below Permissive P-10) or a turbine runback (if .above Permissive P-10 with the IR High Flux trip signal blocked). Any switching sequence performed in the Control Room to meet the Technical Specifications requirements will present some probability of an Engineered Safety Feature (ESF) actuation.

IV. 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 IR NIS High Flux Reactor Trip was an automatic actuation of the RPS.

An assessment was performed considering both the safety consequences and 'implications of this event with the following results and conclusions:

o The two reactor tLip breakers opened as required.

o All control and shutdown rods inserted as designed.

o The plant was stabilized in hot shutdown.

This transient was compared to the transients described in the Ginna Updated Final Safety Analysis Report (UFSAR).

None of the assumptions of the UFSAR were violated during this event. The response of the plant to this transient is bounded by the results of the UFSAR analysis.

Based health on the above, it and safety was assured at can be concluded that all times.

the public's

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