ML20024H344

Summary of Operating Reactors Events Meeting 91-09 W/Utils on 910508 to Discuss Events Which Occurred Since Last Briefing.List of Attendees,Significant Elements of Events Discussed & Reactor Scram Statistics Also Encl

ML20024H344
Person / Time
Site:	Calvert Cliffs, Pilgrim, Waterford, Maine Yankee
Issue date:	05/15/1991
From:	Chaffee A NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Rossi C NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
References
OREM-91-009, NUDOCS 9106030021
Download: ML20024H344 (12)

Text

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NAY 1 5 831 MEMORANDUM FOR:

Charles E. Rossi, Director Division of Operational Events Assessment FROM:

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

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING MAY 8, 1991 - MEETING 91-09 On May 8, 1991, we conducted an Operating Reactors Events meeting (91-09) to inform senior managers from SECY, NRR, OE and regional offices of selected events that occurred since our last briefing on May 1,1991.

lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending 05/05/91. tabulates one significant event which was identified for input into the NRC performance indicator program.

Original signed by 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

• SEE PREVIOUS CONCURRENCE OFC :*EAB:00EA

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NAME : KBaumann: kab:DFischer

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0FFICIAL RECORD COPY 3Fe3 Document Name:

TRANS MEMO 05/08/91

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l MEMORANDUM FOR:

Charles E. Rossi, Director l

Division of Operational Events Assessment FROM:

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

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING MAY 8, 1991 - MEETING 91-09 On May 8,1991, we conducted an Operating Reactors Events meeting (91-09) to inform senior managers from SECY, NRR, and regional offices of selected events that occurred since our last briefing on May 1,1991.

lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending 05/05/91. tabulates one significant event which was identified for input into the NRC performance indicator program.

QIdin3l diDN DI 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 LKilgoce, SECY OFC :EA 00EA,

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fee DATE$05/ l D/91 $ 05/11 /91 $05////91 $05//f/91 0FFICIAL RECORD COPY Document Name:

TRANS MEMO 05/08/91

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CC; T. Murley, NRR (12G18)

D. Wigginton, NRR (11023)

F. Miraglia, NRR (12G18)

T. Quay, NRR (11023)

W. Russell, NRR (12G18)

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 (11819)

J. Richardson, NRR (7026)

A. Thadani, NRR (BE2)

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, RII L. Reyes, RII B. Davis, RIII E. Greenman, RIII R.D. Martin, RIV S. Collins, RIV J.B. Martin, RV R. Zimmerman, RV P. Boehnert, ACRS (P-315)

E. Jordan, AE00 (MN-3701)

T. Novak, AE0D (MN-3701)

L. Spessard, AE00 (MN-3701)

G. Zech, AEOD (MN-3206)

E. Weiss, AE0D (MN-3206)

S. Rubin, AE00 (MN-4106)

M. Harper, AE0D (MN-9112)

W. Bateman, EDO (17G21)

R. Newlin, GPA (2G5)

E. Beckjord, RES (NLS-007)

A. Bates, SECY (16G15) bcc: INP0 ATTN:

J. Cowan 1100 Circle 75, Suite 1500 Atlanta, GA 30339

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL-BRIEFING (91-09)

MAY 8, 1991 NAME ORGANIZATION NAME ORGANIZATION P~~BARAN0WSKY NRR/00EA M ORMAN NRR/PD2-2 D. FISCHER NRR/00EA F. TALBOT NRR/P02-2 D. KIRKPATRICK NRR/00EA K. HART SECY K. BAUMANN NRR/DOEA B. BOGER NRR/DRSP W. LYON NRR/ DST D. WIGGINTON NRR/PO4-2

0. JAFFE NRR/0RP M. CARUSO NRR/SRXB J. BALL NRR/DRIS W. TROSKOSKI OE l

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ENCLOSURE 2

-6 OPERATlNG REACTORS EVENTS BRIEFING 91-09 EVENTS ASSESSMENT BRANCH LOCATION:

10B-11, WHITE FLINT WEDNESDAY, MAY 8, 1991, 11:00 A.M.

WATERFORD 3 LOSS OF SHUTDOWN COOLING WITH RCS PARTIALL.Y FlLLED

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WATERFORD 3 SHUTDOWN COOLING EVENT MAY 5, 1991 PROBLEM:

WITH RCS PARTIALLY FILLED (l' BELOW FLANGE), TRAIN "B" SHUTDOWN COOLING (SDC) WAS LOST.

TRAIN "A" SDC WAS STARTED AFTER 19 MINUTES.

TEMPERATURE ROSE 11 F TO 110 F.

CAUSE:

"A" TRAIN HPSI CHECK VALVE (SEE VALVE DIAGRAN) WAS OPENED FOR REP / IRS ALLOWING AIR TO ENTER SUCTION LINE OF "B" TRAIN SDC PUMP IN USE.

SAFETY SIGNIFICANCE:

LOSS OF SDC COULD HAVE RESULTED IN BOILING AND LOSS OF COOLANT.

A LOSS OF SDC AT THIS SITE IN 1986 RESULTED IN BOILING AND ANOTHER EVENT OCCURRED IN 1988.

BOTH WERE CAUSED BY PROBLEMS WITH LEVEL CONTROL.

DISCUSSION:

O REACTOR WAS IN MODE 5 FOLLOWING REFUELING AND MAINTENANCE.

O-

"A" TRAIN HPSI HOT LEG RECIRCULATION LINE INJECTS DIRECTLY THROUGH A CHECK VALVE INTO THE HIGH POINT (22' ELEVATION) OF THE "B" SDC SUCTION LINE (SEE PIPING DIAGRAM).

THIS LINE IS USED FOR. HOT LEG RECIRCULATION AFTER REFILL FOLLOWING AN ACCIDENT.

CONTACT:

DONALD KIRKPATRICK, NRR/EAB AIT:

NO

REFERENCE:

MORNING REPORT DATED MAY 6, 1991 SIGEVENT:

YES

WATERFORD 3 91-09 i-O WITH REACTOR _ VESSEL LEVEL AT 19', THE HIGH POINT OF_THE "B" SDC SUCTION LINE (AT 22') BECAME FILLED WITH AIR WHEN THE CHECK VALVE WAS OPENED, THUS, CAUSING THE SDC PUMP TO BECOME AIR BOUND.

O TRAIN "A" SDC WAS LINED UP TO FlLL THE REACTOR FROM THE

'RWST.

THE "A" PUMP WAS OFF TO PREVENT INCREASING RCS LEVEL WHICH COULD INTERFERE WITH THE "A" TRAIN HPSI CHECK VALVE WORK.

WHEN TRAIN "B" WAS LOST SHUTDOWN COOLING WAS RECOVERED BY REALIGNING AND VENTING (AS PER PROCEDURE) THE "A"

PUMP.

O UNNECESSARY PERSONNEL WERE EVACUATED FROM THE CONTAINMENT IN ABOUT 15 MINUTES.

THE EQUIPMENT HATCH WAS INSTALLED IN ABOUT 25 MINUTES.

CONTAINMENT WAS CLOSED ABOUT 30 MINUTES AFTER THE START OF THE EVENT.

O THE EVENT INVOLVED A CHANGE IN THE WORK PROCEDURE.

THE PROCEDURE CALLED FOR USE OF FREEZE SEAL BUT AIR IN HPSI LINE WOULD NOT PERMIT THIS.

FOLLOWUP:

O REGION LOOKING INTO WORK CONTROL PROCEDURES AND PLANT CONDITIONS DURING THE REPAIR.

O NRR IS EXPLORING THE QUESTION OF ANY POSSIBLE INTERFACE OF HPSI TRAIN "A" AND SDC TRAIN "B".

O EAB 15 EVALUATING NEED FOR GENERIC COMMUNICATION.

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ENCLOSURE 3 t

IEACTOR SCFAM

SUMMARY

WEIK EhDIN6 05/05/91

!. PLANT SPECIF]C DATA COMPLI- (3 ) fD CATE SITE UNii PCuER 516NAL CAUSE V

YTD YTP CAT 10NS ABDVE PELOW TOTAL 151 151 04/29/91 PAINE YANXEE 1 100 A EQUIPMENT NO 1

0 1

04/29/91 PIL6 RIM 1

30 M EQUIPMENT NO 1

0 1

05/02/91 CALVERT CLIFFS 2

8A EQUIPMENT NO 0

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COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 05/05/91 NUMBER 1991 1990 1989 1988 1987 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCHAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

POWER GREATER THAN 15%

EQUIPMENT RELATED 2

2.4 3.4 3.1 3.0 3.9 PERSONNEL RELATED (2) 0 0.6 0.5 1.0 1.0 1.3 OTHER (4) 0 0.0 0.0 0.1 0.4 1.1 Subtotal 2

3.0 3.9 4.2 4.4 6.3 POWER LESS THAN 15%

EQUIPMENT RELATED 1

0.2 0.4 0.3 0.6 1.2 PERSONNEL RELATED (2) 0 0.2 0.1 0.3 0.4 0.6 OTHER (4) 0 0.0 0.0 0.0 0.2 0.3 Subtotal 1

0.4 0.5 0.6 1.2 2.1 TOTAL 3

3.4 4.4 4.8 5.6 8.4 MANUAL VS AUTO SCRAMS 1991 1990 1989 1988 1987 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

.t%NUAL StrAMS 1

0.8 1.2 0.9 1.1 1.4 AUT011ATIC SCRAMS 2

2.6 3.2 3.9 4.5 7.0

4 NCTES 1.

PLANT SPECIFIC DATA BASED ON INITI AL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.

PERIOD 15 MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.

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

2.

PERSOHt;EL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

3.

COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSON!4EL ERRORS UNRELATED TO CAUSE OF SCRAM.

4.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGil, OR UNKNOWN CAUSE.

OEAB SCRAM DATA Manual and Automatic Scrams fo.- 1987 ------------------ 435 Manual and Autonatic Scrams for 1988 ------------------ 291 Manual and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 fianual and Automatic Scrams for 1991 --(YTD 05/05/91)-- 061

ENCLOSURE 4

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1 C5/07/01 PERFCDANCEINCICATOR$$16N!FICANTEVENTS P;ni hAGE EVENT EVENT DESCRIPilCN GiR SIGNIFICANCE CATE nC;u C1/22/91 RCS INCCRE THl GLE TUlt FAILED AFTER LESS THAN CNE FUEL FCIEWilAL FCR ACILAL IEFACAi:CN OF CYCLE OF SERVICE. THE SAME FAILURE DCCURRED AT DC CCCX FRIMARY COOLANT FRESSURE BCNARY IN JUNE 1990 (FCTEWilAL SENERIC CChCERN)

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