ML20245G542

Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl

ML20245G542
Person / Time
Site:	Palo Verde, Arkansas Nuclear, LaSalle, 05000000
Issue date:	08/03/1989
From:	Haughney C Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-028, OREM-89-28, NUDOCS 8908160082
Download: ML20245G542 (20)

Text

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' 50 G S q MEMORANDUM FOR: Charles E. Rossi, Director

-Division of 0perational Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING August 2, 1989 - MEETING 89-28 On August 2,1989, an Operating Reactors Events meeting (89-2@ was held to brief senior managers from KRR, ACRS, RES, AE00, Consnission Staff, and Regional Offices on events which occurred since our last meeting on July 19, 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. Sunnaries of reactor scrams for the weeks ending 07/23/89 and 07/30/89 are presented in Enclosure 3. One significant event was identified for input into the NRC performance indicator program, o73,gg,1,3,,,, 37 ,

Nrlass J. F.ra::;hwa Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

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J.JJaylor EDO P. Shemanski, NRR E. bckjord, RES

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August 3, 1989 MEMORANDUll FOR: Charles E. Rossi. Director Division of Operational Events Assessment FROM: Charles J. Haughney, Chief Events Assessnent Branch .

Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING August 2. 1989 - MEETING 89-28 On August 2, 1989, an Operating Reactors Events meeting (89-29) was held to brief senior managers from NRR, ACRS RES, AE00, Comission Staff, and Regional Offices on events which occurred since our last meeting on July 19, 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. Sumaries of reactor scrams for the weeks ending 07/23/89 ard 07/30/E9 are presented in Enclosure 3. One significant event was identified for input into the NRC performance indicator program.

Charles J. Ha ney, Chief Events Assesse t Branch Division of Operational Events Assessment

Enclosures:

As stated cr: w/Ec cl. :

See Next Page 1

L l

e s ENCLOSURE 1 LIST-OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-28)

August 2, 1989 NAME ORGANIZATION NAME ORGANIZATION A. Thadani NRR/ DEST J. Roe NRR/DLPQ ,

V. Benaroya AEOD/DSP H. Alderman ACES R. Lobel NRR/00EA C. Posiusny NRR/CRSP K..Connaughton OCM/JC A. Gilbert NRR/DOEA R. Benedict NRR/00EA P. Bobe AEOD/DSP W. Lanning NRR/DRIS- D. Lynch NRR/DRSP L. Olshan NRR/DRSP G. Lainas NRR/DRP E. Rossi NRR/00EA P. Prescott NRR/DLPQ R. Pamirez NRR/DLPQ J. Wechselberger NRR/DLPQ D. Shum NRR/SPLB C. Cel16 Penna NRR/DOEA G. Holahan NRR/DREP S. Diab NRR/CREP

-P. Baranowsky NRR/00EA A. Mattson NRR/DOEA F. Hebdon NRR/DRSP W. Troskeski OE R. Perfetti OE R. Borchardt OED0 M. Ma14oy NRR/CP D. Roberts NRR/DRP L. Kopp NRR/ DEST W. Hodges NRR/ DEST A. Lee NRR/EMTB W. Minners RES/DSIR-C. Haughney NRR/00EA J. Hannon NRR/PD3-3 J. Rit ,ardson NRR/ DEST T. Greene NRR/00EA M. Reardon NRR/00EA T. Chan NRR/PD-5 l

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. ENCLOSURE 2' p

l-L OPERATING REACTORS EVENTS BRIEFING 89-28 f_

EVENTS ASSESSMENT-BRANCH ,

LDfATION: 12B-11, WHITE FLINT WEDNESDAY, AUGUST 2, 1989, 11:00 A.M.

l.

PALO VERDE UNIT 2- OVERPRESSURIZATION OF LOW PRESSURE FEEDWATER PIPING-ARKANSAS UNIT 2 POTENTIAL INTERFACING SYSTEM.

LOCA

-LASALLE UNIT'2 FEEDWATER FLOW CONTROL PROLLEM LEADS TC OPERATION IN POWER / FLOW INSTABILITY REGION-i n

__________._.___.________________._._____._________________________.________.______i_____________..___.________._._____________________.____________...___.__.____________.__._____________.__._._

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PALO VERDE UNIT ~2'

'?" 'OVERPRESSURIZATION OF LOW PRESSURE FEEDWATER-PIPING y # JULY 12, 1989 EEDEU21_ . . .;

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. POTENTIAL! DAMAGE.DUE TO OVERPRESSURIZATION 0F LOW PRESSURE FEEDWATER

'PIPINC.-

a i LAEL LEAKING CHECK-VALVE..

JSAFETY SIGNIFICANCE l RUPTURE OF' LOW PRESSURE PIPING COULD MAKE MAIN FEEDWATER SYSTEM INOPERABLE,'BUT AFW IS STILL AVAILABLE.

j DISCUSSION- q o FOLLOWING REACTOR-TRIP;ON' JULY 12, 1989, WITH. PLANT'IN HOT STANDBY, CONDENSATE /FEEDWATER SYSTEM WAS ALIGNED FOR "LONG-PATH" RECIRCULATION FOR. SYSTEM CLEANUP.

~

o _AUXJLIARY FEE'DWATER SYSTEM PROVIDES DECAY HEAT C00 LING. H 01 CONDENSATE PUMPS PROVIDE. CLEANUP RECIRCULATION.. '!

o AFW; PUMPS. DEVELOP 1580 PSI AT SHUT 0FF. CONDENSATE PUNPS DEVELOP 500. PSI. ll c WHILE. RECIRCULATION ALIGNMENT WAS BEING.MADE, LEAKING CHECK j VALVE-(V 431) PERMITTED AFW PUMP FLOW THROUCH AF/MF SEPARATION j VALVE.(V 097), PRESSURIZING A PORTION 0F hF PUMP SUCTION PIPING.  !

1 cL NO INDICATION TO OPERATORS OF OVERPRESSURE. SIX PRESSURE SWITCHES INDICATED LOW PRESSURE. I 0: PRESSURE SWITCH BELLOWS LEAKED FROM BEING DEFORMEL.

o LICENSEE CHANGED PROCEDURE S0 THAT SEPARATION VALVE IS CLOSED l FIRST. LURING RECIRCULATION ALIGNMENT.

o LICENSEE'S EARLY CALCULATIONS ESTIMATED PIPING H00P STRESSES TO i BE LOW, EbT NO CONSIDERATION OF VALVES, FITTINGS, ETC.  ;

o LICENSEE NOW ANALYZING ALL OVERPRESSURIZED EQUIPMENT MORE FINAL REPORT TO BE COMPLETED BY AbGUST 11, 198S, 1 RIGOROUSLY.

AFTER REVIEW BY INDEPENDENT CONSULTANTS.

l FOLLOWUP TO BE DETERMINED.

. CONTACT: R. BENEDICT SIGEVENT: NO REFERENCEr MORNING REPORT 07/i5/S9, TELECONS 07/27 AND 07/31/89

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. 89-26 ARKANSAS NUCLEAR ONE UNIT 2 POTENTIAL INTERFACING SYSTEM LOCA JUNE 26, 1989 PROBLEM-A CHECK VALVE WHICH ISOLATES SAFETY INJECTION (SI) FROM THE RCS FAILED; ONE CHECK VALVE REMAINED TO PROVIDE OVERPRESSURE PROTECTION.  ;

FOR THE SI SYSTEM. l l

CAUSE CHECK VALVE FAILED DUE TO INSERVICE OPERATION.

I SAFETY SIGNIFICANCE j

THE SI SYSTEM IS ONLY DESIGNED FOR RCS PRESSURE UPSTREAM OF THE TW0.

ISOLATION CHECK VALVES. FAILURE OF THESE CHECK VALVES COULD POTENTIALLY OVERPRESSURIZE THE SYSTEM AND CONSEQUENTLY, CAUSE AN INTERFACING SYSTEM LCCA.

DISCUS 5 ION  ;

i o LICENSEE HAD PREVIOUSLY FCUND PROBLEMS IN THE CUTER ISOLATION CHECK VALVES IN SI LOOPS "A" AND "C".

O AT THE TIME OF THE EVENT, ANO-2 WAS HEATING UP IN MODE 4, FLUSHING-00T THE SHUTDOWN COOLING SYSTEM. ONE LPSI PUMP WAS I l

DEING USED. DISCHARCE WAS TO THE REFUELING WATER TANK (RWT) TO MAINTAIN CONSISTENT BORON CONCENTRATION BETWEEN THE RWT AND RCS.

o LICENSEE OBSERVED PRESSURIZER LEVEL DECREASE UPON DISCHARGE SWITCH FROM RCS TO RWT DURING THE SWITCH FROM NORMAL SHUTDOWN COOLING TO FLUSHING MODE.

AS l o OUTER ISOLATION CHECK VALVE IN SI LOOP "C" DID NOT RESEAT.

A RESULT, THERE WAS BACK-LEAKAGE FROM THE RCS TO THE RWT. l (INNER ISCLATION CHECK VALVE MAINTAINED AS CESIGNED; THEREFORE, LOW PRESSURE SI LINE WAS NOT SUBJECTED TO RCS PRESSURE IN THIS INCIDENT.) THE CHECK VALVE RESEATED BY ITSELF.

SIGEVENT: YES CONTACT: A. GILBERT l

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ARNANSASUNIT2 -

2- 89-28 0 CHECK VALVE.IN LOOP "C" LIFTED A SECOND TIME WHEN THE HPSI PUMPS!WERE.USED TO REFILL THE SI TANKS (ACCUMULATORS). LICENSEE BY RE-ESTABLISHED FLOW TO RCS AND THEN TERMINATED FLOW AGAIN WHICH RESEATED THE CHECK VALVE.

o INVESTIGATIONS BY THE LICENSEE REVEALED THAT THE PIN IN THE LOOP "C" CHECK VALVE WAS MISSING. VALVE WAS REPAIRED.

o BECAUSE OF HISTORY, LICENSEE ALSO CHECKEL LOOP "A" CHECK VALVE AND FCUND THAT Tile PIN WAS CRACKED AND LOOSE. VALVE WAS REPAIRED.

o fiRC WAS NOT' NOTIFIED OF THIS EVENTS HOWEVER, THE LICENSEE IS PROVIDING AN "INFORMATION ONLY" LER.

0 ANO-2 IS NOW AT 100% POWER.

FOLLOWUP o LICENSEE WILL CONDUCT A THOROUGH EXAMINATION OF SI ISOLATION VALVES IN UPCOMING, SCHEDULED (SEPTEMBER 1989) CUTAGE.

O FOLLOWUP BY DEAB IS ONGOING.

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.89-28 LASALLE UNIT 2 FEEDWATER FLOW CONTROL' PROBLEM LEADS TO OPERATION IN POWER /FLCW INSTABILITY REGION AUGUST 1, 1989-PROBLEM WHILE EXPERIENCING REACTOR VESSEL LEVEL CONTROL PROBLEM, THE PLANT.

0PERATED IN A POWER / FLOW INSTABILITY REGION FOR APPROX 15 MINUTES.

CAUSE FEEDWATER CONTROL VALVE PROBLEM CAUSED REACTOR VESSEL LEVEL TO DECREASE. OPERATOR TOOK MANUAL CONTROL OF FEEDWATER AND REEUCED RECIRC PUMP FLOW ENTERING UNSTABLE POWER / FLOW REGION.

SAFETY SIGNIFICANCE THERE WAS A POTENTIAL FOR UNSTABLE THERMAL HYDRAULIC CONDITIONS WHICH COULD LEAD TO CREATER THAN DESIGNED POWER PEAKING FACTORS.

THIS C'ULD 0 LEAD TO VIOLATICU OF THE MINIMUM CRITICAL POWER RATIO L

SAFETY _ LIMIT.

DISCUSSION o LICENSEE FINISHED FEEDWATER LEVEL' CALIBRATION.

o "B" FEEDWATER PUMP WAS ACTING ERRATICALLY IN MANUAL CONTROL.

"A" FEEDWATER PUMP WAS PLACED IN AUTO CONTROL.

o REACTOR VESSEL LEVEL STARTED TO DECREASE AT CONSTANT RATE.

o OPERATOR PLACED "A" FEEDWATER PUMP BACK IN MANUAL, REC 0VERED

' REACTOR VESSEL LEVEL, BUT HAD FEEDWATER OSCILLATION.

o OPERATOR MANUALLY TRIPPED "B" FEEDWATER PUMP, SINCE IT DID NOT APPEAR TO BE RESPONDING CORRECTLY.

o IN ORDER TO STABILIZE LEVEL, OPERATOR LOWERED CORE FLOW WHICH PLACED REACTOR IN "B" REGION OF THE POWER /FLCW MAP INSTABILITY CURVE (REGION "C" IN FIGURE 1 0F NRC BULLETIN 88-07, SUPPLEMENT 1),

o OPERATOR IMMEDIATELY INSERTED PREDEFINED CRAM RODS TO REDUCE POWER AND EXIT INSTABILITY REGION WITHIN 15 MINUTES.

CONTACT: T. CREENE/P. EARAN0WSKY SIGEVENT: TBD.

REFERENCE:

10 CFR 50.72 #16213

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o DURING-THE EVENT, "A" RECIRC FLOW CONTROL VALVE RANBACK AND 1

. CAUSED MISMATCH IN FLOW BETWEEN THE TWO LOOPS..

o OPERATOR COULD NOT GET "A" RECIRC FLOW CONTROL VALVE TO REOPEN-DUE TO HYDRAULIC LOCK CREATED BY THE HIGH DIFFERENTIAL PRESSURE

'ACROSS FLOW CONTROL VALVE AS-A RESULT OF THE RECIRC PUMP RUNNING AT FULL SPEED AND VsLVE IN RUNBACK POSITION.

o -OPERATOR SHUT DOWN "A" RECIRC PUMP,.0PENED FLOW CONTROL.

VALVE AND RESTARTED "A" PUMP.

o IT APPEARS THAT THE OPERATORS FOLLOWED GE RECOMMENDED GUIDELINES FOR EXITING INSTABILITY REGION.

o. REACTOR STABILIZED AT 40% POWER WITH MATCH RECIRC PUMP. FLOW.

o ,llCENSEE HAS VERIFIED THAT N0 INSTABILITIES CCCURRED.

o LICENSEE HAS NOT DETERMINED THE CAUSE OF PROBLEM EXPERIENCED WITH "B" FEEDWATER PUMP.

o RUNEACK OF'"A" RECIRC PUMP WAS CAUSED BY A HIGHER THAN LORMAL LEVEL RESET POINT IN Tl!E RUNBACK LOGIC.

FOLLOWE'P REGION AND NRR ARE CONTINUING FOLLOWING THE EVENT.

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NRC BULLETIN 88-07, SUPPLEMENT 1 FIGURE 1

-DEFENED DPERATING RE01058 tle =

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40 80 80 900 130 8 30 001E FLDr $ OF SA1ED)

REGION A REACTOR 70lfER SREATER TMAN TNE 100% 200 LINE CORE FIDW LESS TRAN 40% OF RATED CORE FWii REGION 3 REACTOR POWER SETWEEN THE 80% AND 1004 30D LINES CORE FWW 1288 TNAN 404 0F RATED CORE RATED REGION C REACTOR POWER SREATER TNAN TNE 804 5t0D LINE CORE FIDN SETWEDI 40% AND 45% OF RhTED CORE FWW 1

_______i_______________._.___._._____.-

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.Page No'. .J1 *

, ENCLOSURE 3-

0B/03/99:

PERFORf C CE INDICATORS S16NIFICANT EVENTS ,.

' PLf2T NAME . EVEFT IEVENTDESCRIPTION GTRSIGNIFICANCE DATE

'. ARKANSAS 2. 06/26/B9SAFETYINJECT10N!! STER (SIS)CHECKVALVE,NHICHISDLATES 0.PDTENTIAL FOR OR ACTUAL DEGRADATION

.LON PRESSURE SIS FROM RCS, FAILED TO RESEAT. PDTENTIAL OF PRIMARY C00LANT PRESSURE FOR DVERPRESSURl!!N6 THE LON PRESSURE S!S AND CAUSINS AN' BOUNDARY INTERFACIN6 SYSTEM LOCA.

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REfCTOR SCRAM

SUMMARY

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' cit ENDO 07/30/09

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2. PLANT SPECIFIC DATA BATE $1TE int!T PONER SIONAL CAUSE COMPLt-- YTD YTD YTD CATIONS 'ABOVE BELON TOTAL 13% 131 NO 1. 1 2 07/24/89 SAN ON0FRE 1 76 M PERSONNEL 3 4 07/26/99 V06TLE 2 100 A EQUIPMENT NO 1 i ,

Yr q

- REACTOR SCRAM SufMARY '

WEEK END]NG 07/23'99 l

!. PLANT SPECIFIC DATA UNIT POWER $16 MAL CAUSE C0f!PLI- YTD YTD YTD DATE SITE CATIONS APOVE BELOW T0tAL 15! 15% ,

w 0 1 1-07/17/09 SAINT LUCIE 1 5A PERSONNEL NO -

3 0 3 l 1 40 M PERSONNEL ND 07/18/89 PIL6 RIM l NO 2 0 2 07/18/89 BRAIDN00D 1 75 A EDU1PMENT NO 2 0 2 07/18/89 BRAIDWOOD 2 84 A E9UIPMENT

! 90 A EQUIPMENT NO 2 -0 2 07/19/89 NORTH ANNA  !

NO 2 0 2 07/21/89 PEACH BOTTOM 2 79 A PERSONNEL 1 0 1 07/21/B9 PRAIRIE ISLAND 1 100 A PERSONNEL MO 1 0 1 07/22/99 GRAND BULF 1 100 A EQUIPMENT ND '

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-II.l COMPARISON.0F WEEKLY STATISTICS WITH: INDUSTRY AVERAGE 5 Q i

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SCRAMS FORLWEEK ENDING 07/30/89 J 1989 1988 -1987 1986 1985-POWER NUMBER f Ll!. 1 SCRAM CAUSE. OF WEEKLY WEEKLY WEEKLY- WEEKLY WEEKLY 1 ~

AVERAGE AVERAGE AVERAGE AVERAGti SCRAMS (5) AVERAGE i ri[- YTD (3)(4). . (8)(9).

• • POWER >15%f 3.1 3.9 4.3 5.4 2.9

>15% 1 2.O' (EGUIP. RELATED 1' 1.3 1.0 1.3 1.8 PERS. RELATED(6) >15% 0.5 1.2 0.4 0. 6 -

>15% 0 0.1

-OTHER(7)

• • ' Subtotal ** 2 4.3 4.6 6.4 '6.5 '8. O '

. ** POWER <15% 0.5 1. 2 ' 1.4 1.3

<15% O' O.4 0.9

. EQUIP..RELATED 0.4 0.3 0.6 0.8

<15% 0 0.2-PERS. RELATED 0 0.0 0.1 0.3 0.2 DTHER <15%

'** Subtotal ** 0.9 '2.1. 2.4 2.4 O- 0.8

• • • Total *** 5.5 8.5 8.9 10.4 2 5.1

~

MANUAL VS AUTO SCRAMS 1989 1988 1987 1986 .1985

TYPE NUMBER WEEKLY OF WEEKLY WEEKLY WEEKLY ~ WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE

.m YTD 1.0 1.4 1.0 1.0 1 0.8 MANUAL SCRAMS 4.5 7.0 7.9 9.4 1 4.2 AUTOMATIC SCRAMS

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b 07/23/89

' POWER NUMBER 1989 ~ -1988 1987 1986 1985 SCRAM CAUSE=

_OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY

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SCRAMS (5) AVERAGE ' AVERAGE AVERAGE AVERAGE AVERAGE YTD- (3)(4) (8)(9) 7.,

,** POWER >15%-

4 3.0 3.1 3.9' 4.3 5.4' EQUIP.-RELATED >15%

3 1.3' 1.0 1.3 1.8. 2.0

.f PERS.'RELATED(6') >15% 0.4 0.6

!I 'OTHER(7). > 15*/. O O .1 ~ 0.5 1.2-1** Subtotal **'

7 4.4 4.6 6.4 6.5 8.O' L , <

• • POWER <15%

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<15% .O O.4 0.5 1.2 1.4 1.3

, lEGUIP. RELATED 0.3 0.6 0.8 0.9.

fPERS. RELATED <15% 1 0.4

<15% 0 0.0 0.1 0.3 0.2 0.2 OTHER.

**' Subtotal **-

.1 0.8 0.9 2 .1' 2.4 2.4

.*** Total ***

8' 5.2 5.5 8.5. 8.9 10.4 e

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[~ MANUAL VS AUTO SCRAME NUMBER 1989 1988 1987 1986. 1985

' TYPE-OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY

- SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD 1 -0.8 1.0 1.4 1.0 1.0 i' MANUAL' SCRAMS. 9.4 7 4.3 4.5 7.0 7.9 AUTOMATIC SCR,AMS

p; - -

Y.! :l, ; a NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS

1. FOR THE. WEEK OF INTEREST.- PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS. REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R00 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. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

3. PERSONNEL RELATED PROBLEMS IHCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

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

h

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