ML20244D279

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Summary of Operating Reactors Events Meeting 89-13 on 890329 to Discuss Events Occurring Since Last Meeting on 890322.Summary of Reactor Scrams for Wk Ending 890326 Encl
ML20244D279
Person / Time
Site: Dresden Constellation icon.png
Issue date: 04/12/1989
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-89-013, OREM-89-13, NUDOCS 8904210252
Download: ML20244D279 (13)


Text

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APR13;m MENORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment j l

1 FROM: Wayne D. Lanning, Chief I Events Assessment Branch I Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING March 29, 1989 - MEETING 89 13 j On March 29, 1989, an Operating Reactors Events meeting (89 13) was held to brief senior managers from NRR, AE0D, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on March 22, 1989.

The list of attendees is included as Enclosure 1.

The events dise_ssed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 includes four significant events identified for input to NRC's performance indicator program and a sunnary of reactor scrams for the week ending 03/26/89.

Wayne . Lanning, Chief {

Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION centesMHet ,

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0FFICIAL RECORD COPY 8904210252 890412 PDR ORG NRRB PNU d

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T. Hurley, NRR B. Siegel, HRR F. Miraglia, NRR D. Muller, NRR J. Sniezek, NRR E. Jordan, AE0D J. Taylor, EDO  !

E. Beckjord, RES W. Russell, RI M. Ernst, RII B. Davis, RIII R. D. Martin, RIV J. B. Martin, RV W. Kane, RI L. Reyes, RII E. Greenman, RIII L. Callan, RIV D. Kirsch, RV

5. Varga. NRR B. Boger, hRR G. Lainas, NRR L. Shao, NRR B. Grimes, NRR F. Cor. gel, llRR E. Weiss, AE00 T. 11artin, EDO J. Lieberman, OE J. Guttmann, SECY A. Thadani, !!RR S..Pubin, AE0D J. Forsyth, INPO R. Barrett, NRR l-l . Harper, AE00 R. Newlin, GPA

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MEMORAllDUM FOR: Charles E. Rossi, Director '

Division of Operational Events Assessment FROM: Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVEliTS MEETING March 29, 1989 - MEETIllC 89-13 On March 29, 1989, an Operating Reactors Events meeting (89-13) was held to

-brief senior managers from NRR, AE00, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on March 22, 1989.

The list of attendecs is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 includes four significant events identified for input to NRC's performance ir:dicator program and a summary of reactor scrams for the week ending 03/26/89.

M Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated

, cc w/ Encl.:

See Ncyt Page l

l i E_ _ -- - - i

" . ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-13)

March 29, 1989 NAME ORGANIZATION NAME ORGANIZATION J. Sniezek DD:NRR K. Kniel RES/DSIR M. Fields .NRR/CPPD J. Raleigh NRR/DOEA C. Lobel. NRR/00EA J. Roe NRR/DLPQ S. Varga NRR/DRP W. Lanning NRR/D0EA M. Virgilio NRR/DRP B. Siegel NRR/PD3-2 J. Clifford OEDO A. Vietti-Cook OCM/LZ l L.J. Callan RIV J. Dyer NRR/DRIS P. Bobe AEOD/DSP D. Muller hRR/PD3-2 i

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ENCLOSURE-2 OPERATJL1R REACTORS EVENTS BRIEFIt'G 89-13 EVEf!TS ASSESSMENT BRANCH

.LOCAT10fl: 12B-11, WHITE FLINT WEDNESDAY, MARCH 29, 1989, 11:00 A.M.

DRESCEN UNIT 3 SCRAM AND LOSS OF 0FFSITE POWER I

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89-13 l DRESDEN UNIT 3 SfEAM AND LOSS OF 0FFSITE POWER MARCH 25, 1989

)

i EEDhlff THE TRIP OF AUXILIARY TRANSFORMER #T32 RESULTS IN A REACTOR SCRAM ON HIGH WATER LEVEL DUE TO THE START OF A STANDBY HAIN FEEDWATER PUMP.

ADDITIONALLY, UPON THE REACTOR TRIP, THE MAIN POWER TRANSFORMER

& AUXILIARY TRANSFORMER #T31 DEENERG12ED CAUSING THE LOSS OF ALL (NON-EMERGENCY) ONSITE E OFFSITE AC POWER FOR UNIT 3.

EhDSE THE INITIATING AUXILIARY TRANSFORMER #T32 ANCMALY RESULTING IM llS FAILURE WAS DUE TO A FAULT ON 345 KV CIRCUIT BREAKER OCB-0-1E.

SAFETY SIGH 1EliaufE THE EVENT APPEARS TO BE OF MINIMAL SAFETY SIGNIFICANCE SINCE ALL APPROPRIATE SYSTEMS WEPE AVAILABLE TO BRING THE UNIT TO COLD SHUTDOWN IN A SAFE MANNER.

DISCUSSIDD o ON MARCH 25, 19ES AT 01:33 HRS (CST) WHILE AT 89% POWER &

STEAEY STATE, lhE UtilT EXPERIENCED AN AUXILI ARY TRANSFORMER

(#T32) TRIP DUE TO A LINE SIDE FAULT ON 345 KV CIRCulT BREAKER OCB C-15.

o THE AUXILIARY TRANSFORMER #T32 ISOLATED RESULTING IN THE AUTC TRANSFER OF HOUSE LOADS TO THE UNIT AUXILIARY TRANSFORMER

  1. T31, c AT THAT TIME, 2 0F 3 MAIN FEEDWATER PUMPS (MFP) "A" & "B" WERE OPERATING WITH THE THIRD, "C" IN STANDBY.

o THE "P MFP TRIPPED ON BUS #T3: LOW VOLTAGE DURING THE AUTO-TRANSFER DUE TO A FAILED AUX 1LIARY CONTACT, CONTACT: J. RALEIGli SIGEVENT: _NO

REFERENCES:

50.72 #'s 15117, 151]E, 15119, PNG-III-89-21, MORNING l REPORT Of MARCH 27, 2005 l

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' DRESDEN UNIT 3 89 '

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O. REACTOR VESSEL LEVEL REACHED 14" BELOW NORMAL AND BEGAN TO RECOVER WITl1 THE AUTO START OF THE "C" MFP.

o WITH THE "C" MFP RUNNING, THE OPERATOR BEGAN TO CLOSE THE "B" FRV T0 COMPENSATE FOR THE FULL OPEN "A" FRV, T111S WAS UNSUCCESSFUL'IN STOPPIhG LEVEL INCREASE.

o REACTOR VESSEL CONTINUED TO INCREASE TO 25" ABOVE NORMAL GENERATING A MAIN TURBINE TRIP AND TRIPPING THE OPERATING MPFs.

o Tile REACTOR TRIPFED FROM 89% POWER DUE TO MAIN TURBINE STOP VALVE CLOSURE AS EXPECTED.

O THE MAIN PCWER TRANSFORMER a AUXILIAFY TRANSFORMER #T31 DEENERG12ED NHEN THE FEACTOR SCRAMMED CAUSIllG LOSS OF BCTH (Il0N-EMERGENCY) ONSITE 8 CFFSITE AC POWER TO UNIT 3.

o UNIT 3 ANC THE UNIT 2/3 SWING DIESEL AUTO STARTED DUE TO BUS UNDERVOLTAGE CONDITIGNS AND RECOVERED ESSENTIAL BUSSES 34-1 E 33-1.

o LPCI SWING EOSSES, 39-7 AND 38-7, ATTEMPTED TO TRANSFER FROM BUS #39 T0-BUS #38.

CONSIDERED. A MALFUNCT10l! DUE TO THE FAllVRE OF A TIMED-0UT UV RELAY TO RESET.

- ADDITIONALLY, THE TRAhSFER FAILED BECAUSE OF FEEDER BREAKER Lil;KAGE BEING OUT OF ALIGNMEl:T.

LPCI WAS NOT REQUIREE THROUGHOUT THE EVENT.

c OPERATOR MAhUALLY ISOLATED THE MSIV's FOR INVENTORY CONTROL INITIATING THE ISOLATION CONCENSER FOR PRESSURE CONTROL.'

o- HPCI WAS MANUALLY INITIATED TO RESTORE REACTOR VESSEL LEVEL AND THE UNIT WAS BROUGHT TO A STABLE COLD SHUTDOWN.

c THE OPERATOR WAS ABLE TO RETURN LEVEL TO 1 INCH FROM THE NORMAL RANGE (+30 TO +35) AND MAINTAINED BETWEEN 800 AND 900 PSIG WITHOUT LIFTING ANY RELIEF VALVES.

o DURING OPERATION OF THE ISOLATION CONDENSER, MAKELlP WAS REQUIRED TO BE TRANSFERRED FROM CLEAN DEMINERALIZED WATER TO TiiE CST (APPROX. 50,00C GAL TOTAL, 10,CCO FROM Tile CST) i

4 eDRESDEtk UtilT 3 89-13 l

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o RESULTED IN A RELEASE VIA THE ISOLATION CONDENSER VENT OF 10-20 MILL 1-CURIES OF MIXED ACTIVATION PROEUCTS'IN STEAM AND )

ENTRAINED WATER.

o LOW LEVEL CONTAMlflATION SPREAD DVER AN EXTENSIVE AREA INSIDEL THE PROTECTED AREA AND OVER A SMALLER AREA (PARKING LOT) JUST.

OUTSIDE'THE PROTECTED AREA FENCE.

O LICENSEE EMPLOYED PREVENTIVE MEASURES PRIOR TO RELEASE, NO PERSONNEL CONTAMINATED.

O AT 8:55, THE LICENSEE RES10 RED OFFSITE POWER, SECURED DIESELS.

AND INITIATED SHUTDOWN TO COLD CONDITIONS.

0FFSITE POWER COULD HAVE BEEN REESTABLISHED EARLIER.

LPCI SWING Bft TROUBLESHOOTING IN PROGRESS AND OCE E-15 REPAIRS COMM F ED MARCH 27, 1989.

SJMIL AR EVESIS o- ISOLATION CONDENSER USE THAT DOES NOT REOUIRE THE TRAliSFER FROM CLEAN DEMINERALIZED WATER HAS, IN THE PAST, RESULTED IN CONTAfi!NATED RELEASE DUE TO THE USE OF CST WATER IN THE MID-70's. ,

o CN JAhUARY 3, 1981, DRESDEN UNIT 2 EXPERIENCED AN EVENT IN WHICH

. CST WATER RESIDUE WAS INTRODUCED INTO THE CLEAN DEMINERALIZED WATER DUE TO A CRUD EURST IN THE.ISCLATION CONDENSER.

THIS EVENT RESULTED IN fi1XED ACTIVATION PRODUCTS BEING RELEASED ANL SPREAD INTO SIMILAR AREAS.

Ef1ATED I_SSUES o DURING THE UfIT 3 EVENT, UNIT 2 REPORTED AN ALERT DUE TO THE LOSS OF ALL ANNUNCIATORS ON CONTROL ROOM ECCS PANEL #902-3.

CAUSE DETERMINED TO BE A BLOWN FUSE DUE TO A BATTERY CHARGER TRIP DN A GROUND FAULT.

UNIT 2 8 UNIT 3 GRIDS WERE C0fiPLETELY JSOLATED FROM EACH OTHER AT TIME OF OCCURRENCE.

ALERT STATUS CIVEN WHEN ANNUNCIATOR PANEL LOST FOR MORE THAN 5 MihbTES.

DETERMJNED NCT TO BE A CONSEQUENCE OF THE UNIT 3 EVENT.

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h DRESLEN UNIT:3 s ' ~89-13'

.o TliE CUESTION WAS RAISED.WHETHER THE UNIT'3 EVENT SHOULD HAVE BEEN REPORTED AS AN UNUSUAL EVENT (UE),

AN UE IS NOT ASSIGNED UNLESS THE LOSS OF THE AUXILIARY TRANSFORMER IS PROJECTED TO OR ACTUALLY EXCEEDS THE TECH i SPEC LCO REPAIR TIME OF 7 DAYS,

- NO UE~ DESIGNAT10f' IS WARRAhTED, ,

L F0LLOliUE REGIONAL PERSONNEL HAVE EEEN DISPATCHED TO SITE FOR FOLLOWU P 0F THE EVENT-ANL~.TO OBSERVE CORRECTIVE AND RESTORATIVE ACTIONS. EAB HAS LETERillfiEE THAT NO FURTHER FOLL0 HUP IS WARRANTEL, E

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f.s 04/03/89= -i FERFORMANCEINDICA70RSSIGNIFICANTEVENTS  : ENCLOSURE 3

  • ; PLAN 7 NAMk - EVENT EVENT DESCRIPTION. OTR SIGNIFICANCE.

DATE SIABLOCANYON1&2 01/17/89 UNREC06N!!ED INOPERABILITY Of AUI FEEDWTER SYSTEM DUE TO 0 POTEWilAL FOR OR ACTUAL DE6RADAT!DN CLOSURE OF ONE OF TWO REDUNDANT STEAM SUPPLY VALVES TO . OF SAFETY-RELATED EQUIPMENT.

TURBINE. '

LASALLE 1 & 2 ' 1t/02/89 FAULT ON UNIT 2 SAT RESULTED IN UNIT 1 REACTOR TRIP W!iH 1 UNEIPECTED PLANT RESPONSE 10 #1tt SUBSEQUENT E3UlFMENT MALFUNCTIONS: INSTRUMENT AIR,. OFCONDIT!DNS.

F C CESS CCMPUTER, CREVAS, ALTERNATE RPS 5REAXERS, AND A RECIFC FCV. AIT TO SITE.

NINE MILE F0lNT 2 02/23/99 LOSS OF OFFSITE F0WER COMBINED WITH SINGLE FAILURE IN 1 1 POTENTIAL FOR OR ACTUAL DE6RADATION' ED6 COULD LEAD TO LCSS OF :nd BECAUSE OF A FAILURE TO' 0F SAFETY-RELATED E0VIPMENT.

I ISCLATE SW TRAINS AND SUBSEQUENT ED6 UNDERC00 LING..

CCNUSED Bf CONTROL LOGIC DESIGN FLAW WHICH SHOULD AUICMATICALLY ISOLATE THE 2 SW DIV.

SAN ONCFFE 1 03/02/59 DESISN EFICIENCY W!iH THE EDS LDAD SEQUENCER LC610. 0 POTENTIAL FOR OR ACTUAL DEGRADAi!0N OF SAFETY-RELA 15D EQU!FMENT.

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+

, . REACTOR SCRAM

SUMMARY

NEEKENDING 03/26/89

1. PLANT SPECIFIC DATA DATE SITE UNIT POWER SIGNAL CAUSE COMPLI- -YTD YTD VfD CAT 10NS ABOVE BELOW TOTAL 151 151 03/22/89 ROBINSON 2 100 A- PERSONNEL NO 1 0 1

.03/22/89 FORT ST. VRAIN 1 0A EQUlPMENT ND 0 1 1

03/23/89 FORT 51. VRAIN 1. OA EQUIPMENT. NO 0 2' 2 03/23/89 FORT ST.VRAIN 1 0A- EQUlPMENT NO 0' 1 1 03/25/09 DRESDEN .3 89 A EQUIPMENT NO 1 0 1 h

9

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< NOTES

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1. PLANT SPECIFIC: DATA BASED ON IlllTIAL REVIEll 0F 50.72 REPORTS FOR THE~ WEEK OF INTEREST. ' PERIOD IS MIDNIGHT SUNDAY THROUGH L MIDNIGHT SUNDAY.- SCRAMS ARE DEFINED AS REACTOR PROTECTIVE.

ACTUATIONS WHICH RESULT'IN.R0D MOTION, AND EXCLUDE PLANNED.-

TESTS OR~ SCRAMS AS PART OF PLANNED SHUTDOWil IN ACCORDANCE llITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN

~

OPERATING LICENSE.

' 2. COMPLICATIONS: REC 0VERY COMPLICATE 0 BY'EQUIPMENTIFAILURES OR:

PERSONNEL ERRORS UNRELATED TO CAU5E OF SCRAM.

3. . PERSONNEL RELATED PROBLEMS IfiCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES,. AND MANUAL STEAli GENERATOR LEVEL CONTROL PROBLEMS.

4.- ' 0THER" INCLUDES- AUTOMATIC SCRAMS ATTRIBUTED T0' Et!VIRONMENTAL -

CAUSES (LIGHTNING), SYSTEM PESIGH,'OR UNKN0tlN CAUSE. l

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