ML20235M167

Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl

ML20235M167
Person / Time
Site:	Limerick, San Onofre, Rancho Seco, 05000000
Issue date:	02/17/1989
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-07, OREM-89-7, NUDOCS 8902280146
Download: ML20235M167 (25)

Text

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FEB 17 It48 r

. 4, MEMORANDUM FOR: Charles E. Rossi, Director L

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

I

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING February 15, 1989 - MEETING 89-07 On February 15, 1989, an Operating Reactors Events meeting (89-07) was held to brief senior managers from NRR, AEOD, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on February 8, 1989.

The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 includes one event suggested for long term followup and two significant events identified for input to NRC's performance indicator program. A summary of reactor scrams is included for the week ending 02/12/89 and for the period 01/01/88 through 12/31/88.

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llayne D. Lanning, Chief Events Assessment Branch

. Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:-

See Next Page DISTRIBUTION t

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DATE :02// 7/89 :02/ IT /89  :  :  :

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8902280146 89021~7 OFFICIAL RECORD COPY PDR ORG NRRB PDC i

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T. Murley, NRR =R. Clark, NRR-

- F.- Miraglia NRR. D. Muller, NRR J.'.Sniezek, NRR G. Kalman, NRR E. Jordan, AEOD G. Knighton, NRR.

'J. Taylor, EDO D. Hickman, NRR 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 S. Varga,-NRR D. Crutchfield, NRR

- B. Boger, NRR G. Lainas, NRR

- G. Holahan, NRR L. Shao, NRR B.~ Grimes, NRR F. Congel, NRR

- E. Weiss, AE0D T. Martin, EDO J. Lieberman, OE-J. Guttmann, SECY A. Thadani, NRR-S. Rubin, AE0D-J. Forsyth, INPO R. Barrett,.NRR M. Harper, AE00 R. Newlin, GPA o

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. UNITED STATES j ' Jr , . i NUCLEAR REGULATORY COMMISSION

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. MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne D. Lanning, Chief i

Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

~ THE OPERATING REACTORS EVENTS MEETING February 15, 1989 - MEETING 89-07 On February 15, 1989, anOperatingReactorsEventsmeeting(89-07)washeldto brief senior managers from NRR, AEOD, RES, Comission Staff, and Regional Offices on events which occurred since our last meeting on February 8, 1989.

The list of attendees is included as Enclosure 4.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 includes one event suggested for long term followup and two significant events identified for input to NRC's performance indicator program. A sumary of reactor scrams is included for the week ending 02/12/89 and for the period 01/01/88 through 12/31/88.

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

Enclosures:

As stated cc w/ Encl.:

See Next Page I

e .

. ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-07)

February 15,1989 NAME ORGANIZATION. NAME ORGANIZATION R. Clark NRR/PD1-2 V. Benaroya ~ AE0D/DSP F. Witt NRR/ DEST- R. Meck NRR/DREP J. Carter NRR/00EA P. Baranowsky NRR/D0EA W. Butler NRR/PD1-2 A. Vietti-Cook OCM/LZ.

-M. .

Harper- AECD W. Troskoski OEDO L. Norrholm CCM/KC A. Toalston NRR/ DEST J. Guillen .NRR/DOEA G. Gears NRR/OSP S. Reynolds NRR/PD-5 G. Kalman NRR/PD-5 G. Holahan- NRR/DRSP C. Rossi NRR/D0EA W. Minners RES/DSIR E. Adensam NRR/DRP J. Roe NRR/DLPQ R. Lobel NRR/DOEA E. Baker NRR/RVIB W. Brach NRR/RVIB M. Reardon NRR/D0EA 1

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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 89-07 EVENTS ASSESSMENT BRANCH LOCATION: 12B-11, WHITE FLINT WEDNESDAY, FEBRUARY 15, 1989, 11:00 A.M.

LIMERICK UNIT 1 FUEL ROD FAILURES SAN ON0FRE UNIT 2 REACTOR STARTUP WITH CORE PROTECTION CALCULATOR ANNUNCIATORS INOPERABLE RANCHO SECO UNIT 1 REACTOR COOLANT PUMP SEAL INJECTION LINE CHECK VALVE INOPERABLE GENERIC ISSUE PART 21 - ASEA BROWN E0 VERI K-LINE CIRCUIT BREAKERS 1

GENERIC ISSUE HARDWARE SPECIALTIES (FASTENER PROBLEMS) (VERBAL-PRESENTATION, N0 SLIDES INCLUDED)

,, 89-07 LIMERICK UNIT 1 FUEL R0D FAILURES FEBRUARY 10, 1989 PROBLEM 33 PINS-IN 3 FUEL BUNDLES HAVE HAD EXCESSIVE CORROSION.

CAUSE SUSPECTED CAUSE IS CRUD INDUCED LOCAL CORROSION (CILC).

SAFETY SIGNIFICANCE FUEL CLAD IS THE FIRST BARRIER TO RELEASE OF FISSION PRODUCTS.

DISCUSSION o EVIDENCE OF FUEL LEAKAGE OBSERVED IN MARCH 1988; PLANT CONTINUED OPERATIONS AT LOWER POWER; DECIDED TO WAIT UNTIL SCHEDULED OUTAGE (JANUARY 1989) TO INVESTIGATE PROBLEM.

o 136 BUNDLES SIPPED: 11 0F 80 BUNDLES FROM RELOAD 1 IDENTIFIED AS LEAKERS, 2 0F 56 BUNDLES FROM INITIAL CORE IDENTIFIED.

o GE IDENTIFIED CAUSE OF FAILURE TO BE CILC. THIS PHENOMENON WAS IDENTIFIED AT VERMONT YANKEE ABOUT 10 YEARS AGO.

o RELOAD 1 FUEL HAS HEAT TREATED CLADDING. THIS IS THE FIRST INSTANCE OF CILC ON THIS TYPE OF CLADDING. GE HAS LOOKED AT.

OTHER PLANTS WITH SIMILAR FUEL AND HAS FOUND NO OTHER INSTANCES OF CILC.

o 15 PLANTS ARE CHARACTERIZED AS "CILC SUSCEPTIBLE". CHARACTERISTICS OF THESE PLANTS ARE:

1. HIGH POWER DENSITY (GREATER THAN 49 KW/L)

2. PRESENCE OF COPPER ALLOY IN CONDENSER.

3. FILTER DEMINERALIZED FOR CONDENSATE CLEANUP (VS DEEP BED DEMINERALIZED).

I o CILC IS CAUSED BY COPPER DEPOSITS ON THE FUEL (USUALLY IN HIGH POWER DENSITY AREA), A GALVANIC REACTION OCCURS; THE COPPER DEPOSIT l LATER SPALLS, LEAVING A BARE SPOT. THE SIZE OF THIS BARE SPOT AND H0LE IN THE CLADDING RANGES FROM 1/8" TO 1/4".

CONTACT: A. MUNN0/R WOODRUFF SIGEVENT: YES

REFERENCE:

MORNING REPORT 02/10/89

LIMERICK UNIT 1 89-07 DI'SCUSSION (CONTINUED) o GE RECOMMENDS THESE PLANTS TO MAINTAIN COPPER LEVELS LESS THAN 0.2 PPB AND N0 HIGHER THAN 0.5 PPB. LIMERICK HAS OPERATED WITH Cu LEVELS IN Tile RANGE OF 0.8 - 1.0 PPB AND OCCASIONAL EXCURSIONS AB0VE 1 PPB.

o LIMERICK BEGAN TESTING DIFFERENT FILTER AND RESIN COMBINATIONS IN JULY 1988. VENDOR-RECOMMENDED PROCEDURES FOR FLOCCULATION OF THE FILTERS ARE CURRENTLY BEING FOLLOWED. FILTER MAINTENANCE IS BEING PERFORMED AS INTENDED.

o Ct.4ROSION IN THE CONDENSER WAS DIMINISHED BY REDUCING AIR INLEAKAGE INTO THE CONDENSER, o FIGURE 1 INDICATES A DROP IN Cu LEVELS DURING 1988.

FOLLOWUP o GE HAS HAD A TEAM ON SITE TO INSPECT FUEL. ANOTHER TEAM WILL ARRIVE SHORTLY TO ANALYZE CRUD COMPOSITION AND LOOK INTO WATER CHEMISTRY.

o LIMERICK IS PLANNING TO REPLACE SUSPECT FUEL ELEMENTS WITH ELEMENTS FROM UNIT 2. THEY ANTICIPATE OBTAINING' REPLACEMENT FUEL FOR  ;

UNIT 2 BY MAY 1989, o OEAD WILL BE MEETING WITH THE PM AND REGION I TO DISCUSS FUTURE ACTIONS.

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SAN ON0FRE UNIT 2 REACTOR STARTUP WITH CORE PROTECTION l CALCULATOR ANNUNCIATORS INOPERABLE FEBRUARY 9, 1989 PROBLEM OPERATORS INITIATED PLANT STARTUP WITH PANEL ANNUNCIATORS INDICATING p CORE PROTECTION CALCULATORS (CPCs) INOPERABLE, CAUSE CPC ANNUNCIATORS DEENERGIZED DURING SHUTDOWN WERE NOT REENERGIZED BEFORE STARTUP, SAFETY SIGNIFICANCE ADMINISTRATIVE CONTROL WEAKNESS AND OPERATOR ERROR LED TO STARTUP WITH OPERABILITY OF CPCs IN QUESTION.

DISCUSSION o ON FEBRUARY 9, 1989, REACTOR STARTUP INITIATED.

.o PANEL ANNUNCIATORS INDICATED CPCs INOPERABLE AND CONSOLE LIGHTS INDICATED CPCs OPERABLE.

o OPERATORS NOTICED DISCREPANCY AND INCORRECTLY ASSUMED PANEL ANNUNCIATORS WOULD CLEAR DURING STARTUP.

o WHEN POWER REACHED 10E-4% AND CPC ANNUNCIATORS DID NOT CLEAR, OPERATORS DECLARED CPCs INOPERABLE AND INITIATED REACTOR SHUTDOWN.

o OPERATOR 0' FAILURE TO BYPASS CONTROL ELEMENT ASSEMBLY CALCULATOR  ;

(CEAC) INPUT TO CPCs DURING SHUTDOWN RESULTED IN A REACTOR TRIP.

o INVESTIGATION REVEALED CPCs TO BE OPERABLE THROUGH THE EVENT.

O CPC ANNUNCIATORS WERE DEENERGIZED DURING SHUTDOWN.

o STATION PROCEDURES DID NOT REQUIRE TAGGING THE CPC ANNUNCIATORS OR KEEPING A WRITTEN RECORD OF CPC ANNUNCIATOR DEENERGIZATION.

O CPC ANNUNCIATORS WERE NOT REENERGIZED BEFORE STARTUP, 1

FOLLOWUP REGION V AND RI ARE INVESTIGATING ADMINISTRATIVE CONTROL FAILURES AND RATIONALE OF OPERATORS IN STARTING-UP WITH ANNUNCIATORS INDICATING CPCs INOPERABLE, CONTACT: D. OUDIN0T SIGEVENT: NO

REFERENCE:

10 CFR 50.72 # 14699 AND MORNING REPORT 02/09/89

,s . .

89-07 RANCHO SECO UNIT 1 REACTOR COOLANT PUMP SEAL INJECTION LINE CHECK VALVE INOPERABLE FEBRUARY 14, 1989 PROBLEM A 2 INCH STOP CHECK VALVE IN THE "B" REACTOR COOLANT PUMP (RCP)

SEAL INJECTION LINE WAS FOUND TECHNICALLY INOPERABLE DURING MAINTENANCE.

CAUSE CLOSURE ASSIST SPRING MISSING. REASON UNKNOWN.

SAFETY SIGNIFICANCE INCREASED RISK OF UNIS0LABLE LEAK OUTSIDE OF CONTAINMENT.

DISCUSSION o' ON FEBRUARY 14, 1989, THE LICENSEE DISCOVERED A CLOSURE ASSIST SPRING TO BE MISSING FROM THE "B" SEAL INJECTION CHECK VALVE.

o OPERABILITY OF THE VALVE IS NOT ASSURED WITH THE SPRING MISSING.

o PIPING QUALIFIED FOR REACTOR COOLANT SYSTEM TEMPERATURES AND PRESSURES UP TO DISCHARGE SIDE OF MAKEUP PUMP.

FOLLOWUP o EAB IS FOLLOW THIS EVENT.

o LICENSEE WILL DETERMINE CAUSE AND CORRECTIVE ACTION.

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l CONTACT: J. THOMPSON SIGEVENT: YES

REFERENCE:

10 CFR 50.72 # 14755 AND MORNING REPORT 02/15/89 a_-

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GENERIC ISSUE PART 21 - ASEA BROWN B0 VERI K-LINE CIRCUIT BREAKERS PROBLEM POTENTIAL FAILURE OF ASEA BROWN B0 VERI K-LINE CIRCUIT BREAKERS (CBs)

TO CLOSE DURING SEISMIC EVENT (ELECTRICALLY OPERATED K-225 THROUGH K-2000 CBs).

l CAUSE MOVEMENT OF SLOW CLOSE LEVER CAUSES JAMMING 0F CIRCUIT BREAKER CLOSING MECHANISM.

SAFETY SIGNIFICANCE FAILURE OF SAFETY-RELATED CIRCUIT BREAKER TO CLOSE ON DEMAND.

DISCUSSION o BROWN B0 VERI SUBMITTED 10 CFR PART 21 NOTIFICATION TO NRC, DATED JANUARY 13, 1989.

o RANCHO SECO QUESTIONED BROWN B0 VERI WHY SOME K-LINE CIRCUIT BREAKERS HAD REB 0UND SPRINGS ON SLOW CLOSE LEVERS.

o DURING SEISMIC TESTING CONDUCTED IN 1974, VIBRATION CAUSED SLOW CLOSE LEVER TO MOVE AND JAM THE CLOSING MECHANISM.

O SLOW CLOSE LEVER IS USED TO ADJUST THE CIRCUIT BREAKER INTERNALS DURING INITIAL INSTALLATION.

o REB 0UND SPRING WAS ADDED BEGINNING IN MID-1974 TO SLOW CLOSE LEVER TO AVOID POTENTIAL JAMMING 0F CIRCUIT BREAKERS.

o IN 1974, BROWN BOVERI DID NOT CONSIDER DEFICIENCY TO BE SIGNIFICANT AND DID NOT NOTIFY THEIR CUSTOMERS.

o BROWN BOVERI HAS RECONSIDERED THE DEFICIENCY AND IS REQUESTING THAT REB 0UND SPRINGS BE ADDED TO CIRCUIT BREAKERS DELIVERED BEFORE JULY 1974.

O BROWN BOVERI HAS NOTIFIED ALL CUSTOMERS WITH SUBJECT K-LINE CIRCUIT BREAKERS IN SAFETY-RELATED APPLICATIONS (18 UTILITIES).

I CONTACT: J. GUILLEN

REFERENCE:

10 CFR PART 21 NOTIFICATION, 10 CFR 50.72 # 14743 i

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GENERIG ISSUE 89-07 ASEA' BROWN B0 VERI K-LINE CIRCUIT BREAKERS 4

DISCUSSION (CONTINUED) o CRYSTAL RIVER REPORTED ON FEBRUARY 13, 1989 THAT TWO K-LINE CIRCUIT BREAKERS WERE NOT SEISMICALLY QUALIFIED DUE TO MISSING' SPRINGS.

FOLLOWUP o GENERIC COMMUNICATIONS IS CONSIDERING AN INFORMATION NOTICE TO INFORM ALL LICENSEES OF DEFICIENCY, SPECIFICALLY COMMERCIAL-GRADE CUSTOMERS.

o VENDOR INSPECTION BRANCH HAS BEEN INFORMED OF NOTIFICATION FOR FOLLOWUP AT THEIR NEXT BROWN B0 VERI INSPECTION.

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LIST OF USERS OF K-LINE CIRCUIT BREAKERS DELIVERED PRIOR TO JULY 1974 Arkansas Power & Light Arkansas Nuclear One Carolina Power & Light Brunswick Cincinnati Gas & Electric Zimmer Consumers Power Palisades Duke Power Oconee Duke Power McGuire f' Florida Power Corporation Crystal River Florida Power & Light St. Lucie Florida Power & Light Turkey Point Indiana & Michigan D. C. Cook

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Iowa Electric Duane Arnold Philadelphia Electric Company Peachbottom Public Service Colorado Ft. St. Vrain Portland General Electric Trojan Public Service Electric & Gas Salem ,

1 SMUD Rancho Seco Virginia Electric Power Company North Anna Virginia Electric Power Company Surry

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1 ENCLOSURE 3 SUGGESTED LONGTERM FOLLOWUP

-02/13/89 SUGGESTED RESOLUTION SUGGEST SIGt T INITIAL FOLLOWUP ASSIGNMENT DAT F PLANT NAME & UNIT '

TRANSFER

-FORMAL ASSIGNMENT BY MEMD -NRR/PRPS T HYDROGEN BURN IN SAFETY 01/16/89 BYRON 2 TO NRR/PRP8. ASSIGNMENT:

INJECTION ACCUMULATOR.

DRAFT AN INF0 NOTICE ON ACCUMULATOR EXPLOSIONS.

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. FERF*FaANCE th0!CATC*3 5:3NIFICANT EVENTS FLt.NT'MME EVENT EVENT :ESCR:FTION CIR 3:3NIFIC;N:E 0 ATE 1::W3 FEU V 1,:, 3 01/31/29 'JFON LC33 CF INSTR'.' MENT ti:4. CCNTAIPENT !!DLAi!CN VALVE O FOTENTIaL F R DE A:T'JAL lE37i:li!*N l'Ai!CH !! A ETTEFFLY VALVE) WILL FAIL IN THE OFEN CF CONTAih*EKi DR EA:E?i-FELATE?

FCili!0N, TR5 'CS'N3

. ONE CF THE CCNTA!hMENT !!3LAi!CN E'EUCTLRES, EARR!ERS. (SIMILAR TC G iH ANNA ; 1 2, MCRNING REFCRT 01!10/B9. SRIEFINS 1 Bi-0:1

3CH: II:3 X'18:39 FE;.:'OR C:"LANT FLMP 3EAL INDECi!CN L:NE CHE X VALIE 2 :CTINi:AL F*; 09 .CT;AL ;EE:,::T!:N IN:FERA!LE, F*RI*AEV::CL W c EI3L:E

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SUMMARY

NEEK EN !NE 02/12/89

1. PLANT SPECIFIC DATA COMFL1- YTD YTD ' YTD TATE SITE UNIT POWER S16NAL CAUSE CATIONS AliCVE BELOW TOTAL 151 151 1 100 A EQUIPMENT NO 2 0 2 02/06/61 HARR:S 0 1 02/06/B9 SA EM 1. 100 A PERSDNNEL NO 1 NO 3 0 3 02/07/89 HAERIS 1 46 A . EQUIPMEWT NO 2 1 3 02/07/69 SUSQUEHANNA 1 1M EQUIPMENT 2 0A PERSONNEL ND 0 1 1 02/09/89 SAN ONOFRE 1 0 1 02/10/B9VDSTLE 1 100 M EQUIPRENT ND 3 0A PERSONNEL ND 0 1 1 02/10/B9 TURKEY POINT 0 1 02/10/B9 SEQUOYAH 1 100 A PERSONNEL NO 1 NO 1 0 1 02/12/B9BEAVERVALLEY 2 65 A EDU!PMENT l

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$ase No. 1 02/14/80>

,i SCRAM

SUMMARY

01/01/88 TO 12/31/88 PLANT NSSS AUTO. AUTO MANUAL MANUAL' SCPAMS TOTAL PLANT CR. HRS' SCRAMS' VEND 0P SCRAMS SCPAMS SCRAME SCRANS WITH SCRANS OPER. / 1000.

>15't (151 4151 (151 COM't . CR. HRS A56ANS45 1 Bk 1 1 0 0 0 2 APFANSAS 1 6157 0.32 4'ANSAS 2 CE 1 0 1 0 0 0,33 2 ARKANSAS 2 6032 BEAVER VALLEY ! W 1 2 0 0 0 3 BEAVER VALLEY 1 7067 0.42 BEAVER VALLEt 2 W- 4 0- 0 0 0 4 BEAVER VALLEY 2 8284 0.48 BIG PDCr PDINT 1 GE 2 1 0 1 0 4 Bl6 ROCr POINT 1 6395 0.63 BRA!0u00D1 .W 2 0 1 0 0 3 BRAIDWD0D 1 3510 0.85 BEAIDWOOD 2 W 7 3 4 1 0 15 BRAl2 WOOD 2 1517 9.89 BR0wNS FERRf 1 6E O O 0 0 0 0 BF0WNS FERRY 1 0 0.00 BROWNS FERRY 2 SE 0 0 0 0 0 0 BRDWNS FERRY 2 0 0.00 BROWNS FEARf 3 BE 0 0 0 0 0 0 BROWNS FERRY 3 0 0.00 BRUNSWICK 1 6E 2 0 0 0 0 2 BRUNSWICK 1 6661 0.30 BRUNSWICK 2 SE 1 1 1 0 0 3 BRUNSWICr 2 5646 0.53 BYPON 1 W 3 0 0 0 0 3 BYRON 1 6485 0.46 BfRON 2 W 4 1 1 0 0 6 BVRON 2 8676 0.69 CALLAWAY I W 4 1 1 0 0 6 CALLAWAY 1 8202 0.73' CALVERT CLIFFS 1 CE 2 0 1 0 0 3 CALVERT CLIFFS 1 6399 0.47 CALVERT CLIFFS 2' CE 2 0 0 0 0 2 CALVERI CLIFFS 2 7827 0.26 CATAWBA 1 W 0 1 0 0 0 1 CATAWBA 1 7070 0.14 CATAWBA 2 W 4 0 4 1 2 9 CATAWBA 2 6497 1.39 CLINTON 1 6E 1 1 1 0 0 3 CLINTON 1 7399 0.41 000r 1 W 3 0 0 0 0 3 COOK 1 8434 0.36 000k 2 W 0 0 0 0 0 0 COOK 2 2716 0.00 COOPER 1 GE 2 0 1 0 0 3 COOPER 1 5968 0.50 CRYSTAL RIVER 3 BW 2 0 0 0 1 2 CRYSTAL RIVER 3 7457 0.27 DAVIS BESSE 1 BW 1 0 0 0 1 1 DAVIS BESSE 1 2127 0.47 DIAk 0 CANYON 1 W 4 2 0 0 0 6 DIABLO CANYON 1 5682 1.06 DIABLO CANYON 2 W 2 0 1 0 1 3 DIABLO CANYON 2 6191 0.48 DRESDEN 2 BE O 0 0 0 0 0 DRESDEN 2 6975 0.00 DPESDEN 3 6E 1 0 0 0 0 1 DRESDEN 3 6346 0.16 DUANE ARNOLD 1 GE f 0 0 0 0 1 DUANE ARNOLD 1 6610 0.15 ,

FARLEY 1 W 1 0 0 0 0 1 FARLEY 1 7428 e.13 FARLEY 2 W 0 0 0 0 0 0 FARLEY 2 8784 0.00 FERMI 2 GE 2 1 0 1 0 4 FERMI 2 5023 0.00 FITIPATRICK 1 SE O O O 0 0 0 FITIPATRICK 1 6061 0.00 FDRT EALHOUN 1 CE 0 0 0 0 0 0 FORT CALHOUN 1 6510 0.00 FORT Si, VRAIN 1 6A 1 0 3 0 0 4 FORT ST. VRAIN 1 3798 1.05 61NNA 1 W 2 1 0 0 1 3 61NNA 1 7679 0.39  ;

GR.E SULF 1 Gi 5 0 1 0 0 6 6 RAND BULF 1 8498 0.71 1 HADDAM NECp 1 W 1 2 0 0 0 3 HADDAM NECK 1 6177 0.49 Ha RIS 1 b 1 0 1 1 0 3 HARRIS 1 6585 0.46 HATCH 1 SE 5 0 0 1 0 6 HATCH 1 A009 1.00 HATCH I 6E 4 1 2 0 0 7 HATCH 2 6359 1.10 H3FE CREEr 1 GE 4 1 1 0 0 6 HOPE CPEEK 1 7090 0.85 INDIAN FDIkT 2 W 3 1 1 0 1 5 INDIAN POINT 2 7492 0.67

' Pace No. . 2 02 /14/E0

• s.

SCRAM

SUMMARY

01/01/88 10 12/31/88 PLANT NS$$ AUTO AU10 MANUAL MANUAL SCRAMS TOTAL PLANT CR. HRS SCRAMS VENICR SCRAN3 SCPAMS SCRAn$ SCRAMS W!ik SCRAMS OPER. /1000

>151 (151 >151 (151 COMPL.

CR. HRS INDIAw. ' J ', W 3 0 1 0 1 4 JNDIAN POINT 3 7313 0.55

.*EmAUNEE 1 W 3 0 0 0 0 3 IEWAUNEE 1 7756 0.39 LACROSSE 1 AC 0 0 0 0 0 0 LACROSSE 1 0 0.00 LAS u l 1 j GE O O O 0 0 0 LASALLE 1 5391 0.00 LASALLE 2 ' BE 1 0 1 0 0 2 LASALLE 2 6648 0.30 LlhEPita 1 BE O 1 0 0 0 1 LINEPICK 1 8476 0.12 MA!hE VAhiEE 1- CE 3 0 0 0 1 3 MAINE YANKEE 1 6950 0.43 MC6018E 1 W 3 0 1 0 0 4 MC6UIRE 1 6784 0.59 MC6UIFE 2 W 0 0 2 0 0 2 MC6UIRE 2 7314 0.27 MILLSIChE 1 GE 1 0 0 0 0 1 MILLSTONE 1 8662 0.12 MILLST0hE 2 CE 1 0 0 0 0 1 MILLSTONE 2 6953 0.14 CILLS10hE 3 W 4 0. 1 0 1 5 MILLSTONE 3 7196 0.69 MONT!CELLD 1 GE 1 0 0 0 0 1 MONTICELLO 1 8769 0.11 NINE MILE POINT 1 GE O O O O. 0 0 NINE MILE POINT 1 0 0.00 NINE MILE POINT 2 GE 6 1 2 0 1 9 NINE MILE POINT 2 2982 3.02 NORTH ANhA 1- W 1 2 1 0 1 4 NORTH ANNA 1 8020 0.50 NORTH ANNA 2. W 0 0 0 0 0 0 NORTH ANNA 2 8735 0.00 DCONEE 1 BW 1 0 0 0 0 1 OC0 HEE 1 B769 0.11 DCONEE 2 fiW D 0 0 0 0 0 DCONEE 2 6989 0.00 000AEE 3 PW 3 0 0 0 0 3 DCONEE 3- 7230 0.41 OYSTER CREEK 1 GE 0 0 0 0 0 0 OYSTER CREEK 1 5789 0.00 PALISADES 1 CE 0 0 0 0 0 0 PALISADES 1 4990 0.00 PALD VERDE 1 CE 5 1 0 0 0 6 PALD YERDE 1 5763 1.04 PALO VERDE 2. CE O 1 0 0 0 1 PALD VERDE 2 5750 0.17 FALO VERDE 3 CE O 0 0 0 0 0 PALO VERDE 3 8202 0.00 PEACH BOTTOM 2 EE O O 0 0 0 0 PEACH BOTTOM 2 0 0.00 PEACH BOTTOM 3 BE 0 0 0 0 0 0 PEACH BOTTOM 3 0 0.00 PfRRY1 BE 4 3 0 0 0 7 PERRY I 6939 1.01 PIL6PIM 1. 6E O O 0 0 0 0 PIL6 RIM 1 0 0.00 POINT liEACd 1 W D 0 0 0 0 0 POINT BEACH 1 7848 0.00 POINT BEACH 2 W 1 1 0 0 1 2 POINT BEACH 2 7708 0.26 PRAIRIE ISLAND 1 W D 0 0 0 0 0 PRAIRIE ISLAND 1 7836 0.00

' PRAIRIE ISLAND 2 W 0 0 0 0 0 0 PRAIRIE ISLAND 2 7814 0.00 00AD C111ES 1 BE 1 0 0 0 0 1 QUAD CITIES 1 8478 0.12 QUAD CITIES 2 SE 2 0 1 0 0 3 00AD CITIES 2 6293 0.4e EANCHO SECD 1 )W 3 0 0 1 0 4 RANCHO SECO 1 5544 0.72 FIVEF l'END 1 GE 4 1 0 0 1 5 P!vER BEND 1 8280 0.60 EL8!NSEN 2 h 3 0 0 0 0 3 R0PINSON 2 5791 0.52 SAlhi LUCIE 1 CE 3 0 0 0 1 3 SAINT LUCIE 1 7554 0.40 SAINT LLCIE 2 (E O O O O O 0 SAlhi LUCIE 2 8784 0.00 SALEM 1 h 1 1 1 0 0 3 SALEM 1 6937 0.43 SA.EM 2 W 6 1 0 0 0 7 SALEM 2 5993 1.17 SAN ONOFFE 1 h 0 0 0 '0 0 0 SAN ONDFRE 1 3010 0.00 SAN ON]FFE 2 CE O O O O O O SAN ON0rRE 2

)

8286 0.00 w_____ x_-- _

i

.Page he. '3' 02/14/09 p SCRAM

SUMMARY

01/01/68 TO 12/31/8B PLANT NSSS' AUTO AUTO MANUAL MANUAL SCRAMS TOTAL PLANT CR. HRS SCRAMS VENDORSCRAM3SCRAMSSCRAMSSCFAMS WITH SCFAMS OPER. / 1000

'151 (151. 1151 (151 CCMFL.

CR. HRS SAN CN7RE 3 CE O O 1 0 0 1 SAN DNOFRE 3 5931 0.17 SEAER00* 1 W 6 0 0 0 0 0 SEAER00K 1 0 0.00 SE000tAH 1 W .2 0 0. 0 0 2 SE000iAH 1 300- 5.26  :!

SEQUOTAH 2 W 4 0 1 0 0 $ SEQUOfAH 2 SkDREHA1 1 5202 0.96 GE O O O Q 0 0 SHOREHM 1 0 0.00 SDdiH TEIAS 1. W 3 1 0 0 0 4 SOUTH TEXAS 1 2497 1.60 SUMMER 1 W '4 0 0 0 0 4 SUMMER 1 6068

. SUREY 1 - W 0.66 2 0 0 0 '0 2 SURRY 1 3755 0.53 SURRf 2 W 1 1 1 0 0 3 SURRY 2 5028 0.60 SUSQUEHANNA1 BE 2 0' 0 0 0 2 SUSQUEHANNA l' i

8290 0.24 SUSQUEHANNA 2 BE - 0 0 0 0 0 TM1 1 0 SUSQUEHANNA 2 6157. 0.00 BW .1 0 0 0 0 1 TM1 1 6761 0.15 TROJAN 1 W 4 0 0 0 0 4 TROJAN 1 5925 0.68 TURKEY POINT 3 W- 0 0 0 1 0 1 TURKEY POINT 3 5400 0.18 TUD EY POINT.4 W  ! 1 0 0 0 2 TURKEY POINT 4- 5050 0.40 I

' YEPMONT 1ANKEE 1 6E 2 1 0 0 0 3 VERMONT YANKEE 1 8404 0.36 V06TLE 1 W 6 0 3 0 0 9 V06TLE 1 6822 1.32 WATERFORD 3 CE 2 1 1 0 0 4 WATERFORD 3- 6625 0.60 WNP 2 BE 1 0 1 0 0 2 WNP 2 6311 0.32 WOLF CFEtk 1 W D 0 0 0 0 0 WOLF CREEK 1 6118 0.00 YANKEE R0WE 1 'W 3 0 0 0 0 3 YAMEE POWE 1. 7487 0.40 IION 1 W 2 2 0 0 0 4 110N 1 6724 0.59 110N 2 W 2 0 0 0 0 2 !!DN 2 -7005 0.29 lit Total ill 192 42 44 8 15 286 l

l l

i

NOTE 5'

1. PLANT SPECIFIC DATA BASED ON IllITIAL REVIEW 0F S0.72 REPORTS

'FOR THE WEEK 0F INTEREST. PEP.IOD IS MIDilIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRANS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R00 MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANilED SHUTDOWN Ill ACCORDANCE WITH A PLAliT PROCEDURE. THERE ARE 111 REACTORS HOLDING Af; OPERATING LICENSE.

2. C0t!FLICATIONS: RECOVERY COMPLICATED BY EQUIPf;ENT FAILURES CR PERSONNEL ERRORS UNRELATEIFTDTAll3E OF SCRAM.

3. PERSONilEL RELATED PROBLEMS IllCLUDE HUMAll ERROR, PROCEDURAL DEFICIENCIES, AllD MANUAL STEAM GENERATOR LEVEL CCllTROL PROBLEllS.

4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIDUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

,