ML20217C512

Summary of Operating Reactors Events Meeting 91-12 on 910626

ML20217C512
Person / Time
Site:	Millstone, Monticello, Dresden, Salem, Oconee, Palo Verde, Catawba, Harris, Grand Gulf, Vermont Yankee, Waterford, Duane Arnold, Yankee Rowe, Big Rock Point, Zion
Issue date:	07/03/1991
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-91-012, OREM-91-12, NUDOCS 9107170170
Download: ML20217C512 (22)

Text

r 1 -

WL 0 31991

.- MEliORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FR0ft: Alfred E. Chaffee. Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS E'IENTS MEETING JUNE 26, 1991 - MEETING 91 12 On June 26, 1991, we conducted an Operating Feactors Events meeting (91 12) to inform senior managers from the Commission staff, NRR, AE0D. ACRS, and regional offices of selected events that occurred since our last briefing on June 5, 1991. Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of_ the discJssed events.

Enclosure 3 contains reactor-scram-statistics for-the weeks ending 06/09/91, 06/16/91, and 06/23/91. Fnclosure 4 tabulaten three significant events which were identified for input into the NRC performance-indicator program.

(original-signed by-David C. Fischer for)-

Alfred E. Chaffee, Chief Events Assessmert Branch-Division of-Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION:

Centra 1-- F iTe's PDR EAB Reading File KBaumann, EAB PBaranowsky, EAB LKilgore, SECY

• SEE PREVIOUS. CONCURRENCE OFC  :*EAB:00EA  :*SL:EAB:DOEA L:EAB DOEA.:0,;1AB 00EA HAME : KBaumann:'kab:DFischer

..:.13d......::............::............::.......

- PBar nowsky : AChaffee '  :  :

DATE :07/ 02 /91 :07/ 02 /91 :07/ g /91 :07/ J- )91  :  :  :

OFFICIAL RECORD COPY Document Name: TRANS ItEli0 06/26/91 1~7MN"5v n . ., '

L,jA;:i~:*/n ,

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F / W RENRM10 REM Nm1" P" 9107170170 910703 PDR- ORO NRRB 0 D Fo 3 PDR $ ) ( l'

d MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessmen FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Everts As essment

SUBJECT:

THE OPERATING REACTORS EVENT 5< MEETING JUNE 26, 1991 - MEETING 91. t On June 26, 1991, we conducted an Operatin Reactors Events meeting (91-12) to inform senior managers from the Commis ion staff, NRR, AC0D, ACRS, and regional offices of selected events the occurred since our last briefing on June 26, 1991. Enclosure lists the attendees. Enclosure 2 presents the significant elements of he discussed events.

Enclosure 3 contains reactor scra statistics for the weeks ending 06/09/91, 06/16/91, and 06/23/91. Enclosu 4 tabulates three significant events which were identified for input into the NRC performance indicator program.

Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION:

Central file PDR EAB Reading File KBaumann, EAB PBaranowsky, EAB LKilgore, SECY OFC :EAB:D0' :5 EAB:DOEA::SL:EAB:DOEA::C:EAB:DOEA NAME : K a r, ann: kab:DF scher :PBaranowsky : AChaffee  :  :  :

DATE :07/p.js/91 :07/c L /91 :07/ /91 :07/ /91  :  :  :

0FFICIAL RECORD COPY Document Name: TRANS MEM0 06/26/91 4

4

z

.- cc:

T.Murley,NRR(12G18) K. Thompson, NRR-(13E16)

F._Miraglia,NRR.(12G18) J. Dyer,NRR-(13E16)

W. Russell, NRR (12G18) P. Sears, NRR (14D1)

F. Gillespie, NRR (12G18)

J. Partlow, NRR (12G18) 5.-Varga, NRR (14E4) -

R. Wessman, NRR (1401)

G.Lainas,NRR(14H3)

B. Boger, NRR (14A2)

J.Zwolinski,NRR(13H24)

M. Virgilio, NRR (13E4)-

D. Crutchfield, NRR (13E4)'

W. Travers, NRR (11B19)

J. Richardson, NRR (7D26)

A.Thadani,NRR(8E2)

F. Rosa, NRR (7E4)

B. Grimes,NRR(9A2)

F. Congel, NRR (10E2)-

- J. Roe, NRR (10H5) ,

M. Pohida, NRR (10E4) '

T. Martin, RI W. Kane, RI C. Hehl, RI S. Ebneter, Ril L. Reyes, Ril B. Davis, R111 E. Greenman, Rill R.D. Martin, RIV S. Collins,-RIV J.B. Martin, RV R. Zimerman, RV P. Boehnert, ACRS-(P-315)

E. Jordan, AE00 (MN-3701 T. Novak, AE00 (MN-3701))

L.-Spessard, AE00 (MN-3701)

G. Zech, AE0D (MN-3206)

E. Weiss,AE0D(MN-3206)

S. Rubin, AE0D (MN-4106)

M. Harper, AE00 (MN-9112)

W. Bateman, EDO (17G21).

R. Newlin, GPA (2GS)

E. - Beckjord, RES (NLS-007)

A. Bates, SECY (16G15) bec: INPO ATTN: J. Cowan 1100 Circle 75, Suite 1500 Atlanta, GA 30339-

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (91-12)

JUNE 26, 1991 NAME ORGANIZATION NAME ORGANIZATION A. CHAFFEE NRR/DOEA R. WESSMAN NRR/PD1-3 ,

T. K0 SHY NRR/DOEA R. DUBE NRR/RSGB  !

D. GAMBERONI NRR/DOEA J. MITCHELL OCM/KC K. BAUMANN NRR/D0EA W. LEFAVE ;NRR/ DST S. SHANKMAN NRR/DLPQ V. BENAROYA. AEOD/DSP K. THOMPSON NRR/PDS P. PRESCOTT NRR/LPEB-D. FISCHER NRR/DOEA P. RAY NRR/DLPQ D, STAMPFL1 RI C. CARPENTER NRR/DLPQ-M. BIAMONTE NRR/DLPQ M. MARKLEY- NRR/DLPQ E. PODOLAK NRR/DREP P.:BOEHNERT. ACRS P. BARAN0WSKY NRR/DOEA M. MILLER RI J. RICHARDSON NRR/DET J. BALL NRR/DRIS  :

T. MURLEY NRR R. SCHOLL NRR/ DST.

J. PARTLOW NRR A. THADANI NRR/ DST B. B0GEP. NRR/DRPW S. RUBIN AE00 C. THOMAS NRR/DLPQ S. VARGA NRR/DRPE E. ROSSI NRR/DOEA B. GRIMES NRR/DRIS.  ;

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. ..,.r , . ~ , -. . . - . . . . . - . , , , . . , _ , . . . . , ~ , . , , . . - _ , -

ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 91-12 EVENTS ASSESSMENT BRANCH LOCATION: 10B-11, WHITE FLINT WEDNESDAY, JUNE 26, 1991, 11:00 A.M.

YANKEE R0WE LOSS OF ALL 0FFSITE AC POWER PALO VERDE 3 INADVERTENT CONTAINMENT SPRAY ACTUATION l

t e e - - 's

91-12 1 YANKEE ROWE LOSS OF ALL 0FFSITE AC' POWER JUNE 15, 1991 PROBLEM:

STAFFING-AND EQUIPMENT CHALLENGES BEYOND ANTICIPATED NEEDS FOLLOWING AN EXTERNAL EVENT.

IAU_SE ~:

-PROBABLY MULTIPLE LIGHTNING STRIKES THAT DISABLED 0FFSITE-POWER AND SOME ELECTRICAL-SUPPORT SYSTEMS.

SAFETY SIGNIFICANCE:

POTENTIAL DELAY ON PLANT REC 0VERY AND EMERGENCY PLANNING-ACTIONS DUE T0 MULTIPLE ELECTRICAL FAILURES.AND FIRE FIGHTING DEMAND.

DISCUSSION:

O LIGHTNING STRIKE HIT'115KV 0FFSITE POWER AND DOWNED BOTH OF THE AC SOURCES.

O REACTOR SCRAMMED FROM 89% POWER DUE-TO REACTOR COOLANT-PUMP LOSS OF POWER.

O FOLLOWING EQUIPMENT / SYSTEMS WERE LOST FROM NON-1E UPS FAILURE.

o SAFETY PARAMETER DISPLAY SYSTEM (SPDS)-

o . SEQUENCE OF EVENTS RECORDER i

o RADIATION MONITORING o MOST OFFSITE= COMMUNICATIONS (ENS, NUCLEAR ALERT SYSTEM)-

CONTACT: THOMAS K0 SHY,- NRR/EAB AIT: NO

REFERENCE:

10 CFR 50.72 #21205, AND- SIGEVENT: YES PNO-I-91-44 f

-YANKEE R0WE' 91-12 0 OTHER: FAILURES o UPS FUSES o LOST 12 PRIMARY AND 24 SECONDARY ANNUNCIATORS o SECURITY COMPUTER -

0 2 0F THE 4 STEAM GENERATOR LEVEL INSTRUMENTATION o LOST MAIN CONDENSER DUE TO BLOWN RUPTURE DISK 0 LOST POWER TO 2 0F 4 FEEDWATER CONTROLLERS o PLANT-PAGER 0 A FIRE AND SM0KE REPORTED IN THE UNIT SWITCHYARD.

O PLANT RECOVERY AND FIRE FIGHTING BECAME A SIMULTANEOUS NEED.

THE SHIFT SUPERVISOR HAD TO DIVERT PART 0F THE FIRE BRIGADE TO MANUALLY START THE STEAM DRIVEN EMERGENCY FEEDWATER PUMP

-(A UNIQUE YANKEE R0WE FEATURE). (THE MOTOR DRIVEN-EMERGENCY FEEDWATER PUMPS ARE NOT AUTO SEQUENCED ON EDGs AND THEREFORE NOT IMMEDIATELY AVAILABLE),

O EMERGENCY NOTIFICATIONS WERE DELAYED RESULTING.FROM COMMUNICATION

~ SYSTEM FAILURE, MARGINAL STAFFING AND OPERATORS' LACK OF FAMILIARITY WITH BACKUP EQUIPMENT.

0 EP PROCEDURES WERE NOT FOLLOWED IN DELEGAT10N10F AUTHORITY TO TECHNICAL SUPPORT CENTER AND EMERGENCY'0FFSITE FACILITY ACTIVATION.

O DOSE ASSESSMENT CAPABILITY WAS LOST FROM A SINGLE FAILURE.

(LOST-RAD.-MONITORS & MET. TOWER)-

0 ONE OFFSITE AC SOURCE WAS REC 0VERED'IN 24 MIN.

O DURING THE OFFSITE POWER RECOVERY TO SAFETY BUSES, A-SAFETY INJECTION (SI) WAS RECEIVED DUE TO IMPROPER BREAKER OPERATION.

(NO INJECTION OCCURRED BECAUSE OF HIGHER PRIMARY PRESSURE)

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

YANKEEIR0WE - 91-12 FOLLOW-UP 0 REGION 1 HAS COMPLETED A SPECIAL TEAM INSPECTION ON THIS EVENT.-

0 GENERIC CONCERNS ARE BEING REVIEWED BY REGION IN THE-F0LLOWING

~

AREAS:

(1) UNANTICIPATED STAFFING NEEDS DUE TO CONCURRENT DEMAND ON FIRE BRIGADE AND PLANT RECOVERYr (2) SUSCEPTIBILITY OF PRIMARY AND BACKUP COMMUNICATION SYSTEMS SINGLE FAILURE; O DEAB WILL REVIEW THIS EVENT WITH THE REGION AND;PEPB FOR PROCESSING ANY GENERIC COMMUNICATIONS, IF-NEEDED, 0 REGION IS CONSIDERING ENFORCEMENT ACTIONS IN EP AND OPERATIONS AREAS.

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YANKEE R0WE 91-12 SEQUENCE OF Eilhl3 i

C/15/91 l'

2350 LOSS OF 0FFSITE POWER AND REACTOR SCRAM i 2355 FIRE BRIGADE DISPITii'TD (INCLUDES ONE SRO) i 6/16/91  !

0010 DECLARED UNUSUAL EVENT (UE) 0014 DNE OFFSITE POWER RESTORLD  ;

0052 NRC NOTIFIED OF UE 0130 DECLARED ALERT  !

0215 NRC NOTIFIED OF ALERT 0450 DE-ESCALATED TO UE l

i 6/17/91  ;

i 0105 PLAtiT IN MODE 4 >

l 0755 PLANT IN MODE 5 [

0925 DE-ESCALATED FROM UE P

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91-12

' I PALO VERDE 3 l INADVERTENT CONTAINMENT SPRAY ACTUATION i JUNE 19, 1991  !

i PROBLEM:  !

AN INADVERTENT CONTAINMENT SPRAY OCCURRED WITH APPR0XIMATELY 3,300 l GALLONS OF RWST WATER BEING SPRAYED. .

.CAUSI: 1 A TEST RELAY HOLD PUSH BUTTON WAS NOT PROPERLY (MECHANICALLY)  !

ASSEMBLED. THIS RESULTED IN IMPROPER PUSH BUTTON OPERATION WHEN t THE BUTTON WAS RELEASED. l SAFETY SIGNIFICANCE:

WETTING 0F COMPONENTS WITH B0 RATED WATER CAN Cl,USE SHORT TERM  !

DEGRADATION SUCH AS ELECTRICAL SHORTS. SINCE SAFETY-RELATED  !

ELECTRICAL EQUIPMENT IS DEdlGNED ACCORDING TO E0 REQUIREMENTS IT l IS GENERALLY NOT SUSCEPTIBLE TO IMMEDIATE DEGRADATION FOLLOWING A FONTAINMENT SPRAY EVENT. HOWEVER, OTHER ELECTRICAL COUIPMENT,

• SUCH AS RCPS, MAY RF AFFECTED.

l LONG TERM EQUIPMENT DEGRADATION IS ALSO POSSIBLE (1.E. ACCELERATED  !

CORROS10N OF CARBON STEEL, DEGRADATION OF OVALIFIED LIFE FOR E0 EOUIPMENT. SNUBBER DEGRADATION, ETC.).

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?

l DISCUSSION: i I

O THE REACTOR WAS OPERATING AT 100% POWER.

0 ESF MATRIX LOGIC FUNCTIONAL TESTS WERE IN PROGRESS.

l CONTACT: DAVID GAMBERON!, NRR/EAB AIT: NO

REFERENCES:

10 CFR 50.72 #21223, MORNING SIGEVENT: NO -

REPORT DATED JUNE 21, 1991, PNO-V-9)-11, AND PNO-V-91-11A l

l 1

PALO VERDE 3 91-12 0 THE FOLLOWING SE0VENCE OF EVENTS OCCURRED: (TIMES ARE MST) 10:02 A.M. THE CONTAINMENT SPRAY SYSTEM WAS ACTUATED.

10:03 A.M. THE CONTAINMENT SPRAY PUMPS WERE SECURED.

10:04 A.M. THE REACTOR WAS MANUALLY TRIPPED IN ACCORDANCE WITH THE ABNORMAL OPERATING (AO) PROCEDURE FOR INADVERTENT CONTAINMENT SPRAY ACTUATION.

10:07 A.M. THE REACTOR COOLANT PUMPS WERE SECURED IN ACCORDANCE WITH THE A0 PROCEDURE. THE PLANT WAS IN NATURAL CIRCULATION, 10:26 A.M. THE CONTAINMENT SPRAY ACTUATION SIGNAL WAS RESET.

11:19 A.M. THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO THE USE OF NATURAL CIRCULATION FOR DECAY HEAT REMOVAL.

THE LICENSEE ENTERED CONTAINMENT TO INSPECT AND MEGGER THE RCPS. THEY FOUND VERY LITTLE WATER IN THE RCP AREA AND THE RCPS WERE MEGGERED SATISFACTORlLY.

12:48 P.M. ONE RCP WAS STARTED.

1:39 P.M. THE UNUSUAL P. VENT WAS TERMINATED BASED ON FORCED CIRCULATION WITH ONE RCP RUNNING.

O THE LICENSEE PROCEEDED TO ENTER MODE 5 TO TROUBLESHOOT THE PROBLEM, O

THE LICENSEE WAS ABLE TO RECREATE A FAULTY SWITCH CONDITION WHICH CAUSED THIS EVENT. THE PUSH BUTTON SWITCH CONTACTS WERE RELEASING THE RELAY HOLD VOLTAGE PRIOR TO REMOVING THE TEST SIGNAL. THIS GENERATED A CONTAINMENT SPRAY ACTUATION, 4

._._.__m. _ _ _ - - - - - _ _ - - - - - - -

FAIO VFRDr 3 91-12 FOLL0\!UP:

0 THE LICENSEE VERIFIED THAT OTHER SIMILAR SWITCHES (IN ALL THREE PLANTS) ARE PROPERLY ASSEMBLED.THERE IS ONE QUESTION REGARDING THE MARKINGS ON ONE PART OF THE SWITCH IN UNIT 1 WHICH WILL BE TESTED TO VERIFY PROPER CONFIGURATION.

O REGION V AND THE RESIDENT STAFF ARE FOLLOWING THE LICENSEE'S ROOT CAUSE ASbESSMENT AND LONG TERM ACTIONS.'

0 NRR/EAB IS EVALUATING THE NEED FOR A GENERIC COMMUNICATION, s

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PALO VERDE 3 4

91-12 CUTLER HAtiER MODEL 10250T-506 PUSHBUTTON ,

SWITCH PUSHBUTTON OPERATOR N

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ENCLOSURE 3 ttAt10R 59 An summAR) utilENtlN606/09/91

1. FL ANT SPttific I4f A(1) pit $1TI t!wli F0t!R l!6nAL CAu$t L0nPL1-(3) fit V10 til, LAllDh5 AfDvt itL0s 101AL

!$1 151 Fikl0hh!L N0 1 1 2 .

06/03/91NAftl$ 1 100 A 10Ullm!NT N0 1 1 2 l' N / M/El m:h11titt0 1 100 A 2 3 06/06/91 M0411t!Lt0 1 0A ftR$0NNEL NO 1 WD 2 0 2 47 A FIRSONNEL 06/09/91t&ti!!N 2 1

3 100 A EDUlFMthi NO 1 0 06/09/91 MILLl10NE 2 1 3 06/09/91 DChtt 3 100 A 10VlFRINT NO I

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~ .__ ___ ....__ _ . _ . ______. _ ____.___._.__._ _ _ __ _ __._ _

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!!. COMPAR!$0N OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 5 4

06/09/91 .

NUMBER 1991 1990 19B9 1988 1987 i 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY l SCRAM cab 3E SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

POWER GREATER THAN 15%

EQU3PMENT RELATED 4 2.4 3.4 3.1 3.0 3.9 PERSONNELRELATED'.!) 1 0.8 0.5 1.0 1.0 1.3 i OTHER(4) 0 0.0 0.0 0.1- 0.4 1.1 i

Subtotal 5 3.2 3.9 4.2 4.4 6.3 POWER LESS THAN 15% ,

EQUIPMENT RELATED 0 0.3 0.4 0.3 0.6 1.2 PERSONNEL RELATED (2) 1 0.3 0.1 0.3- 0.4 0.6 OTHER(4) 0 0.0 0.0- 0.0 0.2 0.3 Subtotal 1 0.6 0.5 0.6 1.2 2.1 TOTAL 6 3.8 4.4 4.8. 5.6 8.4 MANUAL-VS AUTO SCRAMS 1991 1990 1989 1988 1987 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY .

TYPF SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD).

t4ANUAL SCRAMS 0 0.8 1.2 0.9 1.1 1.4 AUTOMATIC SCRAMS 6 3.0 3.2 3.9 4.5 7.0

, .-......._ a,- .. - - , . _ - . - . - - . - . . . . . . . - _ -

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%EACIM $CAAM $U W Ri Nitt Englal N /16/f!

l. PLANT SPitlFlt HTA (3) ..

Mit Slit UNilP0stR$16#4LCoult COMPLI- Vil til Yft (A110#$ AD0VC 9tLOW TOTAL i ,

161 lit -

e 06/11/t1 GRAND $ULF 1 25 A (9U! PENT NO 2 0 2 06/11/91!!DN 2 10 A 19U1PMNT NO 4 1 1 2 06/15/91 Vik@iYANtti 1 -100 A 190lPENT N0 3 0* 3 -

06/1$/91YAhtt!R0st 1 99A EDUIPMui N0 1 9 1 04/16/91 lAllR 1 100 A EDUIPENT NO 1 9. 1 l.

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!!. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES l

l SCRAMS FOR WEEK ENDING 06/16/91 NUMBER 1991 1990 1989 19B8 1987 0F WEEKLY WEEKLY WEEKLY WEE (LY WEEKLY SCRAM CAUSE SCRAMS A'/ERAGE AVERAGE AVERAGE AVEllAGE AVERAGE (YTD)

POWER GREATER THAN 15%

EQUIPMENT RELATED 4 2.5 3.4 3.1 3.0 3.9 PERSONNEL RELATED (2) 0 0.8 0.5 10 3

1.0 1.3 OTHER(4)- 0 0.0 0.0 0.1 0.4 1.1 Subtotal 4 3.3 3.9 4.2 4.4 6.3 POWER LESS THAN 15%

EQ'J1PMENT RELATED 1 0.3 0.4 0.3 0.6 1.2 PERSONNELRELATED(2) 0 0.3 0.1 0.3 0.4 0.6 OTHER(4) 0 0.0 0.0 0.0 0.2 0.3 Subtotal 1 0.6 0.5 0.6 1.2 2.1 TOTAL 5 3.9 4.' 4.8 5.6 8.4 MANUAL VS AUTO SCRAMS 1991 1990 1989 1988 1987 NO. OF WEEKLY WEEKLY LEEKLY WEEKLY WEEKLY TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD).

-MANUAL SCRAMS 0 0.8 1.2 0.9 1.1 1.4 AUT0!iATIC SCRAMS 5 3.1 3.2 3.9 4.5 7.0

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t RIAtiDRS; RAM $UMMARY l

NItt ( 4}N6 06/23/91

1. PLANT $PICIFIC DATA U) .

tAtt 5 fit UNIT Forts l!6kAL CAU$t COMPL1 N kip VfD fit CA110NS A)0VE N LOW TOTAL 151 151 06/17I91 GRA 4 6ULF 1 74 A (DVIFMEhi W3 3 0 3 06/19/91 FALD viitt 3 100 M PERSONhtL ND 1 0 1 W/20/91CATAufA 1 70 A (0U!FMENT NO 1 0 1 06/22/91 DUAh! AKNDLD 1 100 A (0V!FMINI NO 3 0 3 i

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!!. C011 PARIS 0N OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING -

06/23/91 .

NUMBER 1991 1990 1989 1988 1987 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVCRAGE AVERAGE AVERAGE (YTD)

POWER GREATER THAN 151 EQU!PMENT RELATED 3 2.5 3.4 3.1 3.0 3.9 PER50!iNEL RELATED (2) 1 0.8 0.5 1.0 1.0 1.3 OTHER(4) 0 0.0 0.0 0.1 0.4 1.1 Subtotal 4 3.3 3.9 4.2 4.4 6.3 POWER LESS THf.N 15%

EQUIP!1ENT RELATED 0 0.3 0.4 0.3 0.6 1.2 PERSONNEL RELATED (2) 0 0.3 0.1 0.3 0.4 0.6 OTHER (4) 0 0.0 0.0 0.0 0.2 0.3 Subtotal 0 0.6 0.5 0.6 1.2 2.1 '

TOTAL 4 3.9 4.4 4.8 5.6 8.4 1

MANUAL VS AUTO SCRAMS 1991 1990 1989 1988 1987 NO. OF WEEKL Y WEEKL Y WEEKL Y WEEKL Y TYPE WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD) l'AliUAL SCRA115 0.8 1 1.2 0.9 1.1 1.4 l AUTOMATIC SCRAMS 3 3.1 3.2 3.9 4.5 7.0

. _ ... _ _ _ . ~. . _ . . _ ._ _ _ . . _ _ . _ . _ _ _ _ . . _ _ . . _ _ _ . _ _ _ _

j NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD 15 MIDNIGHT SUNDAY THROUGH MIDNIGHT SDNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION,  !

AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLAFNED SHUTDOWN IN l ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN i OPERATING LICENSE.

1

2. PER$0Ni:EL 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. I 4 "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL-CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.- 4 I

I OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ------- ---------- 291 P'nual and Automatic Scrams for- 1989 -------------------252 Manual and Automatic Scrams for 1990 ------------------ 226 ManualandAutomaticScramsfor1991--(YTD06/23/91)--096 f

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ENCE05URE 4 i

P6t M. 1 l'e/jdsis PERFORMANCE IW!!CA10R3 SIGNIFIChi IVIN15

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