ML20059J147

Summary of Operating Reactors Events Briefing 94-01 Conducted on 940105 to Inform Senior Managers of Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931222.Attendees Listed in Encl 1

ML20059J147
Person / Time
Site:	Fermi, Mcguire
Issue date:	01/10/1994
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Grimes B Office of Nuclear Reactor Regulation
References
OREM-94-001, OREM-94-1, NUDOCS 9401310374
Download: ML20059J147 (18)

Text

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January 10, 1994 3 a

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MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support

-FROM: Alfred E. Chaffee, Chief Events Assessment Branch .  ;

Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS. EVENTS BRIEFING ,

JANUARY 5, 1994 - BRIEFING 94-01  !

.a On. January 5, 1994, we conducted an Operating Reactors Events ,

Briefing (94-01) to inform senior managers from offices of the-Chairman, ACRS, OE, OEDO, NRR, AEOD, and regional offices of selected events that occurred since our last briefing on 2 December 22, 1993. Enclosure-1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.

Enclosure 3 contains reactor scram statistics for the year ending-December 31, 1993. No significant events were identified for input into the NRC Performance Indicator. Program, original signed by Alfred E. Chaffee,- Chief Events Assessment Branch-Division of Operating Reactor Support

Enclosures:

As stated cc w/ enclosures:

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• ...* 3anuary 10, 1994 MEMORANDUM FOR: Brian K. Grimes, Director Division of-Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support l

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING JANUARY 5, 1994 - BRIEFING 94-01 l f

On January 5, 1994, we conducted an Operating Reactors Events Briefing (94-01) to inform senior managers from offices of the Chairman, ACRS, OE, OEDO, NRR, AEOD, and regional offices of selected events that occurred since our last briefing on i December 22, 1993. Enclosure 1 lists the attendees. Enclosure 2 ,

presents the significant elements of the discussed events.

Enclosure 3 contains reactor scram statistics for the yea ending December 31, 1993. No significant events were identified for i input into the NRC Performance Indicator Program.  ;

i Od ,'

Alfred E. Chaffee, Chief Events Assessment Branch -.

Division of Operating ,

Reactor Support

Enclosures:

As stated

-i ec w/ enclosures:

See next page  ;

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1

. cc: ,

T. Murley, NRR (12G18) T. Colburn (PDIII-1) i F. Miraglia, NIUt (12G18) A. Blough (PDIII-1) '

F..Gillespie, NRR (12G18) V. Nerses-(PDII-3)

J. Callan, NRR (12G18) L. Plisco (PDII-3)  :

S. Varga, NRR'(14E4)-

J. Calvo, NRR (14A4) ,

G. Lainas, NRR (14H3)

J. Roe, NRR (13E4)  ;

J. Zwolinski, NRR (13H24) i E. Adensam, NRR (13E4)

W. Russell, NRR (12G18)

M. Hodges, NRR (7D26)

A. Thadani, NRR (8E2)

S. Rosenberg, NRR (10E4)

C. Rossi, NRR (9A2)

B. Boger, NRR-(10H3)

F. .Congel, NRR (10E2) ,

D. Crutchfield, NRR (11H21)

W. Travers, NRR (11B19) i D. Coe,LACRS (P-315)

E. Jordan, AEOD (MN-3701) .

G. Holahan, AEOD (MN-9112) i L. Spessard, AEOD (MN-3701) ,

K. Brockman, AEOD (MN-3206) i S. Rubin, AEOD (MN-5219)

M. Harper, AEOD (MN-9112)

G. Grant, EDO (17G21) '

R..Newlin, GPA,(2G5)

E. Beckjord, RES (NLS-007)

A. Bates, SECY (16G15)

T. Martin, Region I W..Kane, Region I R. Cooper, Region I S. Ebneter, Region II E. Merschoff, Region II S. Vias, Region II ,

J. Martin, Region III E. Greenman, Region III J. M11hoan, Region IV B. Beach, Region IV B. Paulkenberry, Region V K..Perkins, Region V q bcca Mr. Sam Newton, Manager i Events Analysis Department  ;

Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 l

, e e e r se

p p 1 .

ENCLOSURE 1 r

LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (94-01)

JANUARY 5, 1994 NAME OFFICE HAlig QFFICE A. CHAFFEE NRR T. MURLEY NRR T. GREENE NRR G. ZECH NRR ,

R. DENNIG NRR R. JENKINS NRR E. GOODWIN NRR M. VIRGILIO NRR-D. SKEEN NRR C. THOMAS 'NRR E. BENNER NRR F. GRUBELICH NRR l J. ROE NRR R. ECKENRODE NRR .;

P. ENG NRR M. CARUSO NRR

'M. CULLINGFORD NRR L. CALLAN NRR J. TSAO NRR B. GRIMES NRR.

W. RECKLEY NRR J. CAINO NRR -

J. GIITTER AEOD J. CARTER NRR  !

S. STEIN NRR J. IBARRA OCM-T. KOSHY- NRR H. BERKOW NRR '

J. MATHIS ACRS D. COE OEDO ,

M.'POHIDA NRR J. BEALL .OE

• L. OLSHAN NRR M. MARKLEY NRR A. HSIA NRR L. PLISCO NRR l E. ROSSI NRR G. WUNDER. NRR M. LESSER RII S. BAJWA NRR L. REYES 'RII F. MIRAGLgA,, NRR.

K. GRAY NRR B. LIAW NRR V. NERSES NRR .

5 TELEPHONE ATTENDANCE (AT ROLL CALL) l i

EngipJla Resident Inspectors Region I Region II Region III ,

Region IV IIT/AIT Team Leaders Misc.

R. Gardner (Fermi)-

M. Lesser (McGuire)

L. .Reyes (McGuire)  ;

I

. ._ _ ._ .. - _ _ . . .. . _ . . ~

.94 MCGUIRE, UNIT 2  :

LOSS OF 0FFSITE POWER WITH COMPLICATIONS DECEMBER 27, 1993  ;

PROBLEM LOSS OF 0FFSITE POWER (LOOP) AND SUBSEQUENT REACTOR SCRAM,.

SAFETY INJECTION (SI), AND STEAM GENERATOR (SG)' DRYOUT.

C8RSE .

LOOP CAUSED BY TWO SWITCHYARD FAILURES. SI CAUSED BY ,

DEPRESSURIZATION OF REACTOR COOLANT SYSTEM (RCS) DUE TO  :

POST-TRIP STEAM LOADS. SG DRYOUT CAUSED BY FAILURE OF l MAIN STEAM ISOLATION VALVE (MSIV) TO CLOSE.

SAFETY SIGNIFICANCE  :

BOTH-OFFSITE POWER SOURCES LOST AND SG TUBES SUBJECTED TO l

-LARGE DIFFERENTIAL PRESSURE.

i SEQUENCE OF EVENTS DECEMBER - 27, 1993 l

22:06:31 525 KV "2B" BUS LOST DUE TO PHASE DIFFERENTIAL i FAULT CAUSED BY INSULATOR FAILURE. TURBINE RUNBACK FAILS TO INITIATE.

l 22:07:00 525 KV "2A" FEEDER LOST WHEN PCB 58 &.59 OPEN l

ON OVERCURRENT DUE TO INADEQUATE RELAY  ;

COORDINATION AND FAILURE OF TURBINE RUNBACK.

1  ;

CONTACT: E. BENNER, NRR/0EAB AIT: 1ES

REFERENCE:

10 CFR 50.-72 #26543 SIGEVENT: IRQ PN0-II-93-076, PNO-II-93-076A ya

.x. - _ .

MCGUIRE UNIT 2 94-01 22:07:07 REACTOR TRIP DN " POWER RANGE HI FLUX RATE" DUE TO VOLTAGE TRANSIENT.

22:07:18 DIESEL GENERATORS (DGs) START.

22:07:20 RCPs TRIP, NATURAL CIRCULATION ENTERED 22:14:04 SI ON " PRESSURIZER LOW PRESSURE" AND " STEAM LINE LOW PRESSURE." HAIN STEAM ISOLATION VALVE (MSIV) "B" FAILS TO CLOSE. ATTEMPTS TO MANUALLY CLOSE THE VALVE WERE UNSUCCESSFUL.

l 22:22 UNUSUAL EVENT (UE) DECLARED.

22:36 OPERATORS ISOLATED AUXILIARY FEEDWATER TO SG "B" IN ACCORDANCE WITH EP03, " MAIN STEAM BREAK OUTSIDE CONTAINMENT".

22:45:49 SG "B" REACHES L0 L0 LEVEL SETPOINT. l 23:26 PRESSURIZER RELIEF TANK RUPTURE DISK RUPTURES DUE TO MASS ADDITION FROM CYCLING 0F PORVs TO l MAINTAIN <1600 PSID ACROSS SG TUBES (PER l WESTINGHOUSE GUIDELINES). STEAM RELEASE CAUSES  !

ICE CONDENSER D0 ORS TO OPEN. l 23:42 0FFSITE POWER BUS "A" RESTORED.

23:45 WIDE RANGE LEVEL INDICATES SG "B" IS DRY.

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MCGUIRE, UNIT 2 94-01 DECEMBER 28, 1993 00:32 4160 V BUSES REALIGNED TO 0FFSITE POWER.

1:37 REACTOR COOLANT PUMP "A" STARTED.

6:22 SECOND OFFSITE POWER SOURCE ESTABLISHED.

12:55 UE TERMINATED WHEN SI LOGIC REINSTATED. SG "B" L0 LO LEVEL TRIP JUMPERED TO ALLOW CLOSING 0F REACTOR TRIP BREAKERS TO REINSTATE SI LOGIC.

RISIRSSION o BUS "2B" INSULATOR FAILURE CAUSED BY SWELLING 0F CORE.

I o BUS "2A" LOST DUE TO INCORRECT RELAY PROTECTION COORDINATION WHICH RELIED ON TURBINE RUNBACK, IN CONJUNCTION WITH A FAILED TURBINE RUNBACK CIRCUIT CARD.

FAILURE ALLOWED A BACKUP NON-DIRECTIONAL RELAY (51L) TO ACTUATE AT 30 SECONDS TO ISOLATE BUS "2A".

o IN 1989, RUNBACK CIRCUIT WAS CHANGED FROM 15 SECONDS TO 3 MINUTES. AT 3 MINUTES, 51L COULD POTENTIALLY ACTUATE EVEN HAD THE RUNBACK FUNCTIONED AS DESIGNED.

o REACTOR COOLANT SYSTEM DEPRESSURIZATION CAUSED BY SUBSTANTIAL POST-TRIP STEAM LOADS, SPECIFICALLY, 14" VALVE 2SM-15, STEAM SUPPLY TO M0ISTURE SEPARATOR REHEATERS, REMAINING OPEN, AND SEVERAL DRAIN LINES FAILING OPEN.

o SHIFT SUPERVISOR ACTIVATED TSC AND OSC TO PROVIDE ADDITIONAL STAFFING FOR EVENT.

MCGUIRE, UNIT 2 94-01 o REPORTING 0F EVENT TO NRC WAS CONFUSED.

MISC 0HMUNICATION EXISTED BETWEEN EXISTING SHIFT AND SUPPLEMENTAL PERSONNEL CONCERNING ACTUAL REPORTING 0F EVENT. PROCEDURE FOR REPORTING NOT IMPLEMENTED.

o TECHNICAL SPECIFICATION STAFFING REQUIREMENTS MET.

o MSIV FAILURE TO CLOSE WAS CAUSED BY MECHANICAL BINDING.

VALVE HAS SPECIFIC TOLERANCES DUE TO SEISMIC DESIGN AND TOLERANCES SHOULD BE SET AND TESTED HOT (PER VENDOR)

VERSUS COLD (AS PERFORMED BY LICENSEE) .

o IN ACCORDANCE WITH EP03, LICENSEE DID NOT FEED

" FAULTED" SG "B", CONSEQUENTLY, SG "B" DRIED OUT.

• I&C PERSONNEL JUMPERED OPEN FOUR CLOSED STEAM DRAIN VALVES DUE TO THE BELIEF THAT THESE VALVES FAILED OPEN AND NEEDED TO BE JUMPERED SHUT. VALVES WERE PREVIOUSLY MODIFIED TO FAIL-CLOSE BUT OPERATORS BELIEVED THEM FAIL OPEN AND DID HOT REFER TO DRAWINGS. DRAWINGS DID NOT SHOW MODIFICATION BUT REFERRED TO MOD PACKAGE.

o MAXIMUM DIFFERENTIAL PRESSURE ACROSS SG TUBES:

1981 PSI.

o IN 1991, UNIT 1 EXPERIENCED A SIMILAR EVENT INVOLVING A LOOP AND SI ACTUATION DUE TO VALVE ISM-15 PROVIDING A i STEAM PATH FROM THE SECONDARY.

o C00LDOWN LIMIT OF 100*F/ HOUR EXCEEDED FOR LOOP "B".

MCGUIRE, UNIT 2 94-01 FOLLOWUP o RESIDENT INSPECTOR RESPONDED TO THE SITE.

o THE LICENSEE DISPATCHED A SIGNIFICANT EVENT INVESTIGATION TEAM FROM ITS CORPORATE OFFICE.

o AUGMENTED INSPECTION TEAM WAS DISPATCHED TO THE SITE.

o EMCB IS EVALUATING THE LICENSEE'S PLANS FOR SG TUBE INTEGRITY EVALUATION.

o OEAB CURRENTLY EVALUATING THE NEED FOR AN INFORMATION NOTICE.

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.94 FERMI, UNIT 2 f CATASTROPHIC TURBINE FAILURE '

DECEMBER 25, 1993 s

ERQRLEM  !

WHILE OPERATING AT 93% POWER, A SUDDEN CATASTROPHIC-  !

FAILURE OF THE TURBINE OCCURRED. IT APPEARS THAT A j TURBINE BLADE OR BLADES BROKE LOOSE FROM THE' TURBINE ROTOR. . PIECES OFEMATERIAL WERE EJECTED THROUGH THE CASING ,i 0F THE NUMBER 3 LOW PRESSURE TURBINE. A SMALL FIRE ENSUED .j NEAR THE GENERATOR EXCITER. u CAUSE  !

- THE ROOT CAUSE OF THE-CATASTROPHIC FAILURE OF-THE TURBINE  ;

IS BEING. INVESTIGATED BY THE LICENSEE. REPRESENTATIVES -

FROM ENGLISH ELECTRIC, GENERAL-ELECTRIC, SALEM AND SAN ONOFRE ARE ONSITE. THE FIRE APPEARS TO HAVE BEEN THE-  ;

RESULT OF A RAPID BURN OF THE HYDROGEN ASSOCIATED-WITH THE GENERATOR.

i SAFETY SIGNIFICANCE '

BROKEN ROTOR AND. LOOSE TURBINE BLADES CAN BECOME MISSILES-AND CAUSE SUBSTANTIAL DAMAGE. THE FIRE PUT-PERSONNEL AND EQUIPMENT AT RISK.

i CONTACT: T. GREENE, NRR/0EAB AIT: YES I

REFERENCES:

10 CFR 50.72'#26536, #26538, SIGEVENT: IBk  !

1. 26540, PN39369, PN39369A, I MORNING REPORTS DTD 12/27/93,  !

12/28/93, 12/30/93, 01/03/94 ]

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FERMI, UNIT 2 94-01 DISCUSSION i

o ON DECEMBER 25, 1993, THE PLANT RECEIVED MULTIPLE TURBINE VIBRATION ALARMS AND A SEISMIC ALARM.

VIBRATIONS WERE FELT IN THE CONTROL ROOM AND THROUGHOUT THE PLANT. THERE WERE LOUD SOUNDS ASSOCIATED WITH THE VIBRATIONS.

o THE TURBINE TRIPPED AND THE REACTOR SCRAMMED. ALL SAFETY SYSTEMS FUNCTIONED AS EXPECTED.

o MAIN STEAM ISOLATION VALVES CLOSED ON CONDENSER HIGH PRESSURE.

o REACTOR PRESSURE WAS CONTROLLED VIA SRVs AND REACTOR VESSEL WATER LEVEL VIA RCIC AND STANDBY FEEDWATER SYSTEM.

o GENERATOR HYDR 0 GEN GAS PRESSURE DROPPED TO ZERO.

o SM0KE AND STEAM WERE NOTICED IN THE TURBINE ROOM.

LICENSEE DECLARED AN ALERT AND SUSPENDED SECURITY REQUIREMENTS FOR SOME PERSONNEL RESPONDING TO THE EVENT (PERSONNEL NOT SEARCHED).

o THE LOCAL FIRE DEPARTMENT WA3 SUMMONED TO THE SITE, BUT IT WAS NOT NECESSARY FOR THEM TO ENTER THE PLANT.

o A SMALL FIRE AT THE BRUSHES OF THE GENERATOR EXCITER WAS PUT OUT USING FIRE EXTINGUISHERS.

- _ _ +

FERMI, UNIT 2 94-01 o A 2 INCH TURBINE BUILDING EQUIPMENT COOLING LINE WAS SEVERED DURING EVENT. THIS AND THE ACTIVATION OF THE SPRINKLER SYSTEM RELEASED A LARGE AMOUNT OF WATER MIXED WITH OIL ON THE MAIN AND LOWER TURBINE DECK. ABOUT 17,000 GAL OF TURBINE LUBRICATION OIL AND HYDROGEN SEAL OIL WAS RELEASED IN THE TURBINE BUILDING.

o CONDUCTIVITY IN THE REACTOR INCREASED, DUE TO SEVERED CONDENSER TUBES. THE MAXIMUM VALUE WAS 180 MICROMHOS (T.S. LIMIT IS 10 MICROMHOS). ,

o PLANT COMMENCED A C00LDOWN RATE OF 15 DEGREES FAHRENHEIT PER HOUR.

o WHEN ATTEMPTING TO PLACE DIVISION II SHUTDOWN COOLING IN SERVICE, THE "B" RECIRCULATION PUMP DISCHARGE VALVE WOULD NOT FULLY CLOSE. SHUTDOWN COOLING USING THE "A" LOOP WAS INITIATED.

e ON 12/26/93 PLANT ENTERED COLD SHUTDOWN.

FOLLOWUP o LICENSEE FOUND A PIECE OF MATERIAL THAT BROKE THROUGH THE TURBINE CASING OF THE HUMBER 3 LOW PRESSURE TURBINE 75 FEET FROM IT. THE MATERIAL IS ASSUMED TO BE PART OF A TURBINE BLADE.

o THERE WAS EVIDENCE THAT THE HYDR 0 GEN USED FOR COOLING THE MAIN GENERATOR HAD BURNED AND DAMAGED GENERATOR COMPONENTS.

LFERMI, UNIT 2 94-01 ,

a o THERE IS LARGE AMOUNT OF OIL THROUGHOUT THE TURGINE l

- BUILDING. THE LICENSEE HAS POSTED FIRE WATCHES.  ;

o A BROKEN WIRE WAS FOUND IN THE LIMITORQUE. HOUSING OF THE "B" RECIRCULATION PUMP DISCHARGE VALVE.

o LEAD STAFF FOR AN AUGMENTED INSPECTION TEAM WERE l DISPATCHED TO THE SITE. TEAM LEADER IS RON GARDNER.

MAJORITY OF THE TEAM WILL BE ONSITE 01/10/94 WHEN TURBINE INVESTIGATION BEGINS.

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Enclosure 3 DEACTOR SCRAM Reporting Per1od: 12/27/93 to 12/31/93 YTD YTD  ;

ABOVE BELOW YTD QAlj, PLANY & LINit POWi# M CAUSE 0

[.MPLICATIONS' 18 j)J M 12/27/93 MCGulpt 2 100 SA Equipnent Failure . YES 3 0 3 1

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Cote: Year To Date (YTD) Totals include Events within the Calendsr Year Indicated By The End Date of the Specified Reporting Period EI5*10 Page:1 01/05/94-

DEstRIPTION OF COMPLICATION ($) . 12/27/93 70 12/31/93 ,

1111 WN,Q COMPLICAff0NS MCGd!PE 2 MSIV FAILED TO CLOSE (JPON LOS$-OF OFFSITE POWER. ' ONE STEAM CENERATOR B01 LED ORY.

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I COMMRis0N OF WEEKLY SCRAM $1Atl5 TICS WitM lNDUSTRY AVERAGES  ;

PERIOD ENDING '

12/31/93 i WUMBER 1993 1992 1991* 1990* 1989* '

0F WEEKLY WEEKLY WEEKLY WEEKLY WEKLY  ;

$CRA* CAUSE SCRAM 5 AVERAGE AVERAGE AVERAGE AVERAGE AVERACE- ,

(110)

POWER GREATER THAN OR fouAL TO 15%

ECUlPMEW1 FAILURE

• 1 1.8 2.6 2.9 3.4 3.1 'I DESIGh/1R$fALLAT10N ERROR

• 0 0.0 - - - -

l OPERATING ERROR

• 0 0.3 0.2 0.6 0,5 1.0 l

0.5 0.4 MAistthANCE ERROR

• 0 - - -

ExtERwAL* 0 0.1 - - - -

01NER* 0 0.0 0.2 - -

0.1  ;

l Subtorat 1 2.7 3.4 3.5 3.9 6.2 ,

power LESS THAM 15%  ;

EQulFMEhi FAILURE

• 0 0.4 0.4 0.3 0.4 0.3 i DESIGb/lW51ALLATIoh EREOR* 0 0.0 - - -

OPER A11NG ERADR* 0 0.1 0.1 0.2 0.1 0.3 MAltilhAuE E RROR* 0 0.0 0.1 - - -

EXTERhAL* O 0.0 - - - -

OTHER* O 0.0 0.1 - - -

subteta1 0 0.5 0.7 0.5 0.5 0.6 J

^l 10iAL 1 3.2 4.1 4.0 4.4 4.8 ,

i 1993 1992 1991 1990 1989 l kO. Of WEErLY WEEKLY WEEKLY WEEKLY WEEKLY ,

5? RAM TV3 $CRANS AVE R AGE AVE R AGE AVERAGE AVE R AGE AVERAGE (TTD) 701AL AUTOMATIC $ CRAM $ 1 2,4 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAML 0 0.9 1.0 0.7 1.2 0.9

.t 70TALS MAY OlFFER BECAUSE OF Rouw0!NG ofF 1

• Detailed breakdown net in database f or 1991 and eart ter r

- Ex1ERkAL cause inctWed in Ecu!P*ENT FAILURE  ;

a MAINTEhANCE ERROR and OESIGN/jkSTALLA110N ERROR causes included in OPERAtlhG ERROR otrER ceae included in Ecu1PHEst F AltuRE 1991 and 1990 t

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. . . . . . - .~.

J NOTES

1. PLANT SPECIFIC DATA' BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.

SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.

2. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.. -

3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

4. "OTHER" INCLUDES AUTOMATIC SCW ,.MS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, % UNKNOWN CAUSE.

OEAB SCRAM DATA '

Manual and Automatic Scrams for 1987 ------------------ 435  ;

Manual and Automatic Scrams for 1988 ------------------ 291 '

Manual and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ----------------- -212 Manual and Automatic Scrams for 1993 --(YTD 12/31/93)-- 176 .

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[ Enclosure 2 OPERATING REACTORS EVENTS BRIEFING 94-01 LOCATION: 10 Bil, WHITE FLINT WEDNESDAY, JANUARY 5, 1994 11:00 A.M.

MCGUIRE, UNIT 2 LOSS OF 0FFSITE POWER WITH COMPLICATIONS (AIT)

FERMI, UNIT 2 CATASTROPHIC TURBINE FAILURE (AIT)

PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR

-)