ML20056D984

Summary of Operating Reactors Events Meeting 93-17 on 930512

ML20056D984
Person / Time
Site:	Oconee, Perry, Indian Point, Vermont Yankee, Vogtle, Comanche Peak
Issue date:	05/18/1993
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Grimes B Office of Nuclear Reactor Regulation
References
IEB-79-13, IEB-93-002, IEB-93-2, IEIN-82-29, IEIN-92-071, IEIN-92-71, IEIN-93-020, IEIN-93-034, IEIN-93-20, IEIN-93-34, OREM-93-017, OREM-93-17, NUDOCS 9308190138
Download: ML20056D984 (26)

Text

', ' . m MAY 181993 m w w 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 MAY 12, 1993 - BRIEFING 93-17 On May 12, 1993, we conducted an Operating Reactors Events Briefing (93-17) to inform senior managers from offices of the ACRS, OE, NRR, RES, SECY, AEOD, and regional offices of selected events that occurred since our last briefing on April 28, 1993.

Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.

Enclosure 3 contains reactor scram statistics for the weeks '

ending May 2, 1993 and May 9, 1993. No significant events were identified for input into the NRC performance indicator program.

1

- original signed by Robert L. Dennig for -

Alfred E. Chaffee, Chief Events Assessment Branch .

Division of Operating l Reactor Support I

Enclosures:

As stated DISTRIBUTION:

Central Files EGoodwin cc w/ attachments: PDR DSkeen See next page EAB R/F JCarter KGray RBenedict RDennig NFields LKilgore, SECY EAB/ DORS 0

EAByDORS hOS EAB/ DOR'S E j KGray RDennig EGoodwin AChaffa '

es'/gy /93 (/h/93 f //j /93 [//f/93 l OFFICIAL RECORD COPY DOCUMENT NAME: ORTRANS.KAG (G:KAG)

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9308190138 930518 PDR ORG NRRB PDR g)[ y . ,__ ; '

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T. Murley, NRR (12G18) R. .Stransky (PDIII-3)

F. Miraglia, NRR (12G18) J. Hannon (PDIII-3) .;

F. Gillespie, NRR.(12G18) F._ Williams (PDI-1).  ;

J. Partlow,iNRR (12G18) R. Capra:(PDI-1).

S. Varga, NRR (14E4) 'L. Raghavan (PDII-2)

J. Calvo,.NRR (14A4) H. Berkow (PDII-2)

.G. Lainas, NRR (14H3) l J. Roe, NRR (13E4) _

J. Zwolinski, NRR (13H24). <

M.' Virgilio, NRR (13E4)

W. Russell,.NRR-(12G18) ,

J. Richardson, 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).

D. Coe, ACRS (P-315) -  !

E. Jordan, AEOD'(MN-3701) _

Acting Director, DSP/AEOD (MN-9112) i L. Spessard, AEOD (MN-3701) ~

'K. Brockman, AEOD (MN-3206)  ;

S. Rubin,-AEOD (MN-5219) .;

M._ Harper, AEOD (MN-9112) i i

'G. Grant, EDO. (17G21)

R. Newlin, GPA-(2G5) ,

E. Beckjord, RES (NLS-_007 ) 3 A. Bates,.SECY (16G15).  ?

G. Rammling, OCM-(16G15) {

T.' Martin, Region I -i W. Kane,. Region I C. Hehl, Region I  ;

S. . Ebneter, Region II j E. Merschoff, Region II 't

S. Vias, Region II j J. Martin, Region III j

-E.-Greenman, Region III  !

-J. Milhoan, Region IV  !

B.~ Beach, Region IV ,i B. Faulkenberry, Region V :l K. Perkins,_ Region V  ;

i bec: 'Mr. Sam Newton, Manager

. {

Events Analysis' Department .

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

-I 4

ENCLOSURE 1 LIST OF ATTENDEES t

OPERATING REACTORS EVENTS FULL BRIEFING (93-17)

MAY 12, 1993 NAME OFFICE NAME OFFICE J. CARTER NRR R. CAPRA NRR R. BENEDICT NRR J. RAJAN NRR N. FIELDS NRR J. KUDRICK NRR A. CHAFFEE NRR C. ROSSI NRR K. GRAY NRR S. VARGA NRR R. DENNIG NRR S. LONG NRR E. GOODWIN NRR T. KIM NRR M. WILLIAMS NRR V. HODGE NRR D. MCDONALD NRR V. BENAROYA AEOD H. BERKOW NRR W. TROSKOSKI OE M. BANIC NRR N. KADAMBI RES -l S. ROSENBERG NRR D. COE ACRS ,

S. BLACK NRR K. HART SECY J. NORBERG NRR TELEPHONE ATTENDANCE  !

(AT ROLL CALL)

Reaions Resident Inspectors Region I Perry Region II Indian Point Region III Turkey Point -

Region IV Region V >

IIT/AIT Team Leaders Misc.

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i OPERATING REACTORS EVENTS BRIEFING 93-17 LOCATION: 10 B11, WHITE FLINT l WEDNESDAY, MAY 12, 1993, 11:00 A.M. l I

i i

PERRY RESIDUAL HEAT REMOVAL STRAINER  !

(UPDATE) i l

1 INDIAN POINT, UNIT'2 LOOSE PARTS IN STEAM GENERATOR l TURKEY POINT, UNIT 4 STEAM GENERATOR FEEDWATER N0ZZLE- ,

T0-REDUCER CRACKS  ;

-PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION 0F OPERATING REACTOR l SUPPORT, NRR

i 93-17 j PERRY  !

RESIDUAL HEAT REMOVAL STRAINER l (UPDATE) )

APRIL 7, 1993  :

i i

PROBLEM  :

TWO STRAINERS LOCATED IN THE SUPPRESSION POOL ON THE 1 SUCTION LINE TO THE RESIDUAL HEAT REMOVAL (RHR) PUMPS HAD DEFORMED.  !

CAUSE:

DEBRIS AND DIRT HAVE COLLECTED ON THE STRAINERS DURING  !

OPERATION OF THE RHR PUMPS.

SAFETY-SIGNIFICANCE i

. DEGRADATION DURING NORMAL OPERATION MAY HAVE REDUCED i OPERATING MARGIN.. CORE COOLING FLOW.DURING/FOLLOWING.AN 1 ACCIDENT / TRANSIENT MAY-BE REDUCED UNEXPECTEDLY TO LOWER THAN REQUIRED TO PRECLUDE FUEL DAMAGE. THE RHR-PUMPS:

COULD-BE DAMAGED AND MADE-INOPERABLE BY OPERATING.WITH -l INSUFFICIENT-NPSH AVAILABLE. SUPPRESSION POOL COULD-OVERHEAT, THEREBY IMPACTING CONTAINMENT COOLING. I 1

DISCUSSION l e LICENSEE USED A REMOTE CONTROLLED. CAMERA TO INSPECT l THE SUPPRESSION' POOL'IN MAY 1992.. DEBRIS.WAS- j IDENTIFIED AND DISPOSITIONED'FOR REMOVAL DURING NEXT~

i REFUELING OUTAGE. THE STRAINERS LOCATED ON.THE-END OF.

1

~ '

THE RHR SUCTION LINE-WERE SUBSEQUENTLY"0BSERVED.T0 BE j' DEFORMED'IN. JANUARY 1993 DURING-A MID CYCLE' OUTAGE.

. CONTACT: J. CARTER, NRR/ DORS AIT: NO 1

REFERENCE:

. -10 CFR 50.72 #25415 SIGEVENT: TBD l l

g PERRY 93-17 )

e LICENSEE IN JANUARY 1993 DURING A MID-CYCLE OUTAGE i BEGAN TO REMOVE THE DEBRIS AND CLEAN THE SUPPRESSION POOL l DEBRIS WAS PRIMARILY DIRT DEBRIS WAS DISLODGED BY A WATER JET j POOL WAS CLEANED BY VACUUMING THE BOTTOM AND y

REMOVING LARGE OBJECTS UPON REMOVAL OF- DEBRIS FROM STRAINERS, DEFORMATION. .i WAS IDENTIFIED AND DAMAGED STRAINERS REPLACED.  !

I e NONCONFORMANCE REPORT EVALUATIONS OF DEFORMATION WERE DISCUSSED WITH NRR DURING. ROUTINE COMMUNICATIONS. j e SITUATION DISCUSSED IN INSPECTION REPORT 92-26, DATED I FEBRUARY 12, 1993. j e PROBLEM WAS ELEVATED.WITHIN NRR BY TECHNICAL STAFF l

. FOLLOWING AN INSPECTOR MEETING IN REGION III IN  !

MARCH 1993 WHEN IN 92-71, " PARTIAL. PLUGGING OF 1 SUPPRESSION POOL STRAINERS AT A FOREIGN BWR," WAS l DISCUSSED.

• A REACTOR BLOWDOWN EVENT OCCURRED AFTER THE :l JANUARY 1993 CLEANING. -

• STRAINERS WERE INSPECTED AGAIN, MID APRIL-1993,-AND THE .

j RHR S NER WAS FOUND.TO HAVE. COLLECTED DEBRIS AND.

-* IN 93-34, ADDRESSING PERRY STRAINER DEBRIS PROBLEM, WAS l ISSUED APRIL 26, 1993.- l I

t o o PERRY 93-17 e AN EXTENDED FLOW TEST WAS CONDUCTED TO DETERMINE EFFEC OF LONG TERM OPERATION WITH A STRAINER HAVING DEBRIS PRESSURE AT PUMP SUCTION DECREASED FROM INITIAL DYNAMIC READING OF 6 PSIG TO 0 PSIG AFTER 8 HRS OF OPERATION A REPEAT OF THE TEST USING IMPROVED INSTRUMENTATION HAD SIMILAR RESULTS I

- HPSH WAS SUFFICIENT FOR PUMP TO DELIVER REQUIRED FLOW DURING THE TEST e A SUBSEQUENT ANALYSIS SHOWED THE DEBRIS TO BE PRIMARIL GLASS FIBERS AND CORR 0SION PRODUCTS SIMILAR TO FIBERS USED IN ROUGHING FILTERS USED IN THE DRYWELL COOLERS e SUPPLEMENT 1 TO IN 93-34 WAS ISSUED MAY 6, 1993 TO ADDRESS UNPROTECTED FIBROUS MATERIAL IN THE DRYWELL.

CORRECTIVE ACTION '

e LICENSEE 1) REMOVED ALL ROUGHING FILTERS FROM THE DRYWELL AND CONTAINMENT AREA

2) IS REPLACING ALL STRAINERS WITH A NEW DESIGN TO WITHSTAND 32 PSID AND LARGER l 1

H0LES, AND EMERGENCY CORE COOLING SYSTEM STRAINERS HAVE BEEN ENLARGED TO TWICE THE SURFACE AREA,

3) HAS CLEANED THE POOL AND ALL SURFACES AB0VE THE P0OL 0F DIRT AND DEBRIS

4) DEVELOPED A PROCEDURE TO PERMIT BACK-FLUSHING THE STRAINERS

5) IS DEVELOPING IMPROVED INSPECTION STANDARDS AND SURVEILLANCE TECHNIQUES.

e

. . 9 .

PERRY 93-17

• NRC ISSUED BULLETIN 93-02 THAT REQUESTS REMOVAL OF FIBROUS MATERIAL NOT DESIGNED TO WITHSTAND A LOSS-OF- i COOLANT ACCIDENT AND REQUIRES REPORTING THEIR ACTIONS.

REPRESENTS THE NEED FOR IMMEDIATE ACTION AND l REFLECTS ONE ELEMENT OF OVERALL PROGRAM e NRR PLANS TO QUANTIFY THE SAFETY SIGNIFICANCE OF 'i PLUGGED STRAINERS. .

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INDIAN' POINT, UNIT 2 .!

LOOSE PARTS IN STEAM GENERATOR l' MAY 2, 1993

-i PROBLEM  ;

LOOSE PARTS FROM REACTOR INTERNALS COLLECTED IN STEAM i GENERATOR INLET HEAD.

CAUSE  !

FAILURE OF CONTROL ROD GUIDE TUBE SUPPORT PIN DUE TO  !

POSSIBLE CORROSION.

SAFETY SIGNIFICANCE e POTENTIAL DAMAGE TO STEAM GENERATOR TUBES, TUBE PLUGS (WESTINGHOUSE AND B&W) AND T0'OTHER- REACTOR COOLANT l SYSTEM COMPONENTS. a e POTENTIAL GUIDE TUBE MISALIGNMENT AFFECTING CONTROL ROD ,

MOTION. 1 i

DISCUSSION  :

e NOISE HEARD ON LOOSE PARTS MONITOR DURING PLANT STARTUP j AFTER REFUELING OUTAGE. ]

l e .THREE:-PIECES FROM' GUIDE TUBE SUPPORT STRUCTURE 1 RECOVERED FROM ONE' STEAM GENERATOR INLET HEAD: 1 v SUPPORT PIN NUT-  !

v v-

- LOCKING DEVICE l

' DOWEL' PIN-CONTACT: R. BENEDICT,.NRR/ DORS AIT- TBD 1

REFERENCE:

PLANT STATUS REPORT DATED SIGEVENT:- TBD:

05/03/93 j

O . . O INDIAN POINT, UNIT 2 93-17 e INSPECTION SHOWED EVIDENCE OF IMPACTS ON TUBE ENDS AND PLUGS.

• MINIMAL DAMAGE DUE TO EARLY SHUTDOWN AND REMOVAL OF LOOSE PARTS.

• SIMILAR EVENTS HAVE OCCURRED AT OTHER PLANTS, SOME WITH GREATER DAMAGE TO STEAM GENERATOR.

• NRC INFORMATION NOTICE 82-29 ADDRESSES PREVIOUS OCCURRENCES.

• SAFETY EVALUATIONS BY WESTINGHOUSE, B&W, AND LICENSEE INDICATE GUIDE. TUBE WILL REMAIN PROPERLY ALIGNED WITH

FAILED SUPPORT PIN, NO SIGNIFICANT CHANGE IN-CONTROL ROD DROP TIMES, NO SIGNIFICANT DAMAGE FROM LOOSE PARTS, AND STARTUP AND POWER OPERATION IS ACCEPTABLE FOR THE NEXT OPERATING CYCLE.

e LICENSEE CONDUCTING INVESTIGATION TO DETERMINE FUTURE ACTIONS.

FOLLOWUP REGION I, LICENSEE, WESTINGHOUSE AND NRR (REACTOR SYSTEMS, MECHANICAL ENGINEERING, MATERIALS ENGINEERING, REACTOR PROJECTS) DISCUSSED THE EVENT AND THE SUPPORTING 10 CFR 50.59 EVALUATION ON MAY-7, 1993. NO SIGNIFICANT SAFETY ISSUES WERE IDENTIFIED TO PRECLUDE RE-START.0F'THE UNIT.

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93 -

TURKEY POINT, UNIT 4 1 STEAM GENERATOR FEEDWATER i N0ZZLE-TO-REDUCER CRACKS l APRIL 1993 l PROBLEM _ l CRACKS WERE FOUND IN ALL THREE STEAM GENERATOR. (SGF .i

.FEEDWATER N0ZZLE-TO-REDUCER WELD JOINTS AT-TURKEY POINT, l UNIT 4. .

CAUSE j UNDER~ INVESTIGATION, LICENSEE SUSPECTS THERMAL FATIGUE. j

^

SAFETY SIGNIFICANCE CRACKS IN THE FEEDWATER REDUCER-COULD-LEAD'TO A FEEDWATER  !

LINE BREAK IN THE EVENT.OF A SEISMIC EVENT OR:A WATER.  :

HAMMER. A FEEDWATER LINE BREAK RESULTS IN A LOSS OF A 1 REACTOR COOLANT SYSTEM HEAT SINK AND WOULD RESULT IN i RELEASE OF STORED' ENERGY FROM THE SG INTO CONTAINMENT. j DISCUSSION e; . CHRONOLOGY OF EVENTS: j

~

v MAY/ JUNE 1979 - BULLETIN 79-13 INSPECTIONS  !

COMPLETED, NO:INDICATI0ii 0F CRACKS NOTED l v' l JUNE 1980 - CRACKS FOUND IN: ALL THREE UNIT 4 REDUCERS. ALL' REDUCERS REPLACED ALONG'WITH SOME- 1 PIPING SPOOLS i d

i CONTACT: N. FIELDS, NRR/ DORS AIT: NO i

REFERENCE:

- N/A- SIGEVENT: TBD -!

~. . . .-. ,

g e l TURKEY. POINT, UNIT 4 93-17 v OCTOBER 1980 - CRACKS FOUND IN ALL UNIT 3 REDUCERS.

ALL REDUCERS REPLACED

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v 1981-1982 - UNIT 4 SG REPLACED, AT LEAST TWO REDUCERS WERE REUSED  !

v 1982-1983 - UNIT-3 SG REPLACED. NO.. RECORD OF L WHETHER REDUCERS WERE REUSED l i

v APRIL 1984 - ROUTINE ULTRASONIC TESTING (UT)

REVEALS CRACKS IN ALL THREE-UNIT 4 REDUCERS. WELD l DESIGN WAS MODIFIED AND ALL REDUCERS-REPLACED  ;

v MAY 1984 - UT OF UNIT 3 REDUCERS SHOWS NO  !

INDICATIONS; HOWEVER, WALL THINNING EVIDENCED IN

~

i REDUCER COUNTER BORE AREA WELD BUILDUP TO RESTORE l WALL THICKNESS  !

l v APRIL 1993 - UT DETECTS CRACKS IN ALL THREE. UNIT 4-  !

SG REDUCERS.

e THE CRACKS ORIGINATED-IN OR:NEAR THE N0ZZLE-TO-REDUCER ,

WELD ROOT AND PROPAGATED AT ABOUT.A 45 DEGREE ANGLE- 1 INTO THE REDUCER BASE MATERIAL FOR ALL-THREE.SGs. THEL j CRACKS WERE CIRCUMFERENTIAL AND PRIMARILY AT.THE  !

~ TOP OF THE 18 INCH DIAMETER END 0F THE REDUCER. 1 j

v SG A: LARGEST CRACK APPROX. 10 IN., MAX 50%- _

j THROUGH-WALL. THREE-OTHER MUCH SMALLER CRACKS ON  !

THE SIDE  !

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TURKEY POINT, UNIT 4 93-17 v SG B: LARGEST CRACK APPR0X. 20 IN. CRACK, MAX. 40%

THROUGH-WALL, AT THE TOP. FOUR OTHER HUCH SMALLER CRACKS ON SIDES AND BOTTOM.

v SG C: TWO LARGEST CRACKS APPROX. 8 IN. MAX. 40%

THROUGH-WALL, AT THE TOP. FOUR OTHER HUCH SMALLER CRACKS ON SIDES AND BOTTOM e UT INSPECTIONS OF THE AFFECTED AREAS IN 1988 AND 1991 REVEALED NO INDICATIONS OF CRACKS.

• THE LICENSEE NOTED N0 UNUSUAL OPERATING CONDITIONS DURING THE 1991-1993 OPERATING CYCLE THAT WOULD HAVE ACCELERATED THE CRACKING.

FOLLOWUP e THE LICENSEE IS IN THE PROCESS OF REPLACING ALL THREE REDUCERS WITH LIKE MATERIAL.

• SAMPLES OF THE REDUCERS HAVE BEEN SENT OFFSITE FOR METALLURGICAL ANALYSIS TO VERIFY THAT THE CRACKING RESULTED FROM THERMAL FATIGUE AND N0 NEW FAILURE MODE HAS DEVELOPED.

e NRC INFORMATION NOTICE 93-20, " THERMAL FATIGUE CRACKING 0F FEEDWATER PIPING TO STEAM GENERATORS," WAS ISSUED MARCH 24, 1993.

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• e ENCLOSURE 3 REACTOR SCRAM Reporting Pertod: 04/26/93 to 05/02/93 YTD VfD ABOVE BELOW YTD gjQ C@PLICATIDWS j)] j}J 1918,(

E PLAWT & t*ff lYP[. [A321 OC3iEE 2 0 Equipment Failure No 1 2 3 04/29/93 SM l

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l l Eot e: Year To Date (YTD) Totals Ireld Events Within The Calender Year traficated By The End Date of The speelfled Reportirig Period ETS-10 Page:1 05/04/93

'. a e-CEMFARISDN OF WEEKLY SCRAM S1 ATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 05/02/93 WJMBER 1993 1992 1991* 1970* 1989*

OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCna" CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

POWER GREATER TkAN OR EQUAL TO 15%

EQUTPMENT FA! LURE

• O 2.2 2.6 2.9 3.4 3.1 DESIGN /INSTALLAfl0N ERROR

• 0 0.1 - - - -

OPERATING ERROR

• 0 0.3 0.2 0.6 0.5 1.0 MAINTENANCE ERROR

• O 0.5 0.4 - - -

EXTERNAL

• 0 0.2 - - - -

OTHER* 0 0.0 0.2 - -

0.1 SWtetal 0 3.3 3.4 3.5 3.9 4.2 PCMER LESS THAN 15%

EoulPMENT FAILURE

• 1 0.5 0.4 0.3 0.4 0.3 DESIGN /lkSTALLATION ERROL* O 0.0 - - - -

OPERATING ERROR

• 0 0.1 0.1 0.2 0.1 0.3 MAINTEhANCE ERROR

• O 0.0 0.1 - - -

EXTEnkAL' O 0.0 - - - -

01HER* 0 0.0 0.1 - - -

$@ total 1 0.6 0.7 0.5 0.5 0.6 10iAL 1 3.9 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 WO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM YYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

TOTAL AU10MA110 SCRAMS 0 2.6 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 1 1.3 1.0 0.7 1.2 0.9 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF

• Detailed breakdown not in database for 1991 and earlier

- EXTERNAL cause incluoed in EQUIPMENT F AILURE MAINTENANCE ERROR and DESIGN /INSTALLAfl0W ERROR causes included in OPERATING ERROR OTHER cause inclukd in EQUIPMENT FAILURE 1991 and 1993 ETS-14 Page: 1 05/04/93 1

- 1

!-

• n U

Om . .

REACTOR ECRAM l Reporting Period: 05/03/93 to 05/09/93 ,

YTD YTD ABOVE BELOW YTD E81[ Pt AWt & WIT FMR ILPI CAVSE ECMPLICAT!ows 1 11 ji) E .;

99 SA Maintenance Error No 1 1 2 C5/03/93 V0GTLE 1

":uWCHE PEAK 2 23 SM Egalpment Falture No 1 0 1 CS/04/93 I

t i

h hot;: Year To Date (YTD) Totals include Events Within The Celerder Year Indicated By The Erd Date of The Specified Reporting Period

!TS-1D Page:1 05/13/93

a g w . .

CONFARISDN OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 05/09/93 1991* 1990* 1989*

NUMBER 1993 1992 WEEKLY WEEKLY WEEKLY OF WEEKLY WEEKLY AVERAGE AVERAGE AVERAGE AVE R AGE AVERAGE 1; RAW CAU11 SGRAMS (YTD)

PDWEa GREATER THAN OR EQUAL TO 15%

2.9 3.4 3.1 1 2.1 2.6 EDUlPMENT F AILURE* - - -

O 0.1 -

DESIGN /lkSTALLATION ERROR

• 0.5 1.0 O 0.3 0.2 0.6 DPERATING ERROR * - -

1 0.5 0.4 -

MAINTENANCE ERROR * - -

O 0.2 -

EXTERNAL * - 0.1 O 0.0 0.2 -

OTHER*

3.4 3.5 3.9 4.2 Subtotal 2 3.2 POWER LESS TNAN 15%

0.4 0.3 0.4 0.3 O 0.4 EQUIPMENT FAILURE * - - -

0 0.0 -

DESIGN /lNSTALLATION ERROR

• 0.1 0.3 O 0.1 0.1 0.2 OPERATING ERROR * - - -

O 0.0 0.1 MAINTENANCE ERROR * - - -

EXTERkAL* O 0.0 -

O 0.0 0.1 OTHER*

0.7 0.5 0.5 0.6 0 0.5 Subtotal 4.1 4.0 4.4 4.8 TOTAL 2 3.7 1991 1990 1989 1993 1992 WEEKLY WEEKLY WEEKLY No. OF WEEKLY WEEKLY AVERAGE AVERAGE AVERAGE SCRAMS AVERAGE AVERAGE SCRAM TYRE (YTD) 3.1 3.3 3.2 3.9 TOTAL AUTOMAT!C SCRAMS 1 2.6 1.0 0.7 1.2 0.9 1 1.2 TOTAL KANUAL SCRAMS TOTALS MAY DIFFER EECAUSE OF ROUND!kG OFF

• Detailed breake?wn not in dstabase f or 1991 and earlier

- EXTERNAL cause included in EQUlPMENT F AILURE

- MAlhTENANCE ERROR and OESIGN/INSTALLAT!DN ERROR causes included in OPERATING ERR

- OTHER cause included in EDL'IPMENT F AILURE 1991 and 1990 05.

PaDe: 1 ETS-14

k NOTES o . .

O 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'AEACTORS HOLDING AN OPERATING LICENSE.

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

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

3. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING) , SYSTEM DESIGN, OR UNKNOWN CAUSE.

OEAB SCRAM DATA (2nual and Automatic Scrams for 1987 ------------------ 435 (2nual and Automatic Scrams for 1988 ------------------ 291 (2nual and Automatic Scrams for 1989 ------------------ 252 (anun1 and Automatic Scrams for 1990 ------------------ 226 (anual and Automatic Scrams for 1991 ------------------ 206 (anual and Automatic Scrams for 1992 ------------------ 212 (nnual and Automatic Scrans for 1993 --(YTD 05/09/93)-- 70

.