ML20147E362

Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl

ML20147E362
Person / Time
Site:	Indian Point, Columbia, Brunswick, 05000000
Issue date:	02/28/1988
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-88-008, OREM-88-8, NUDOCS 8803070044
Download: ML20147E362 (20)

Text

I L

MEM00,ANDUM FOR: Charles E. Rossi. Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation l

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING February 23, 1988 - MEETING 88-08 On February 23, 1988 an Operating Reactors Events meeting (88-08) was held to brief senior managers from NRR, RES AE00 and Regional Offices on events which occurred since our last meeting on February 16. 1988. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. The Enclosure 3 presents a tabulation of long-term followup assignments to be completed and a sumary of reactor scrams. No events were suggested for long term followup. No significant events were identified for input to NRC's performance indicator program. Enclosure 4 provides a 50.72 report tabulation and sumary for February 15 through February 22, 1988.

I Wayne Lanning. Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation  ;

Enclosures:

As stated cc w/Enclo.:

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H,Bg6 W MEMORANDUM FOR: Charles E. Rossi. Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning, Chief l

Events Assessment Branch I Division of Operational Events Assessment Office of Nuclear Reactor Regulation

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING February 23. 1988 - MEETING 88-08 On February 23, 1988 an Operating Reactors Events meeting (88-08) was held to brief senior managers from NRR. RES. AE00 and Regional Of fices on events which occurred since our last manting on February 16, 1988. The list of attendees is included as Enclosure 1.

The events discussed and the tignificant elements of these events are presented in Enclosure 2. The Enclosure 3 presents a tabulation of long-term followup assignments to be completed and a summary of reactor scrams. No events were suggested for long term followup. No significant events were identified for l input to NRC's performance indicator program. Enclosure 4 provides a 50.72 report tabulation and summary for February 15 through February 22, 1988.

Wayne Lanning, Chief '

Events Assessment Branch Division of Operational Events Asstissment Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/Encio.:

See Next Page

L

. cc:

T. Nurley J. Sniezek F. Miraglia J. Forsyth. INPO E. Jordan M. Slosson E. Jordan R. Capra E. Beckjord R. Samworth W. Russell, RI G. Knighton B. Davis, RIII E. Sylvester J. Nelson Grace, RII E. Adensam R. D. Martd.n, RIV J. B. Martin, RV W. Kane", RI L. Reyes, RII C. Norelius, RIII J. Callan, RIV D. Kirsch, RV S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan L. Shao J. Partlow B. Grimes F. Congel E. Weiss S. Black T. Martin J. Stone R. Hernan H. Bailey J. Guttmann A. Thadani S. Rubin v . _~ .

~

l l

ENCLOSURE 1 I

i LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-08)

February 23, 1988 l NAME ORGANIZATION NAME ORGANIZATION W. Lanning NRR/DOEA S. Varga NRR/DRP R. Lobel NRR/DOEA E. Adensam NRR/PD II-I K. Eccleston NRR/ADR-2 T. Silko AEOD D.M. Crutchfield NRR/DRSP G. Klingler NRR/PMAS R. Capra NRR/PD I-I F. Gillespie NRR/PMAS H.L. Slosson NRR/PD I-I R. Wright NRR/ADR-4 F. J. Miraglia NRR/ADP B. Grimes NRR/DRIS J. Zwolinski NRR/DLPQ V. Benaroya AEOD/DSP M.L. Reardon NRR/DOEA J. Heltemes AEOD R. Scholl NRR/00EA D. Tondi NRR/ DEST B. Reckley AEOD/IRB F. Rosa hRR/SELB B. Stransky AEOD/DOA G. Holahan NRR/DRSP P. Baranowsky NRR/DOEA E. Sylvester NRR/DLPQ 1 V. Beraroya AEOD/DSP J. Roe NRR/DLPQ G. Gears OSP J

f.

. Et4 CLOSURE 2 0PERATING REACTORS EVENTS BRIEFING 88-08 TUESDAY, FEBRUARY 23, 1988, 11:00 A.M.

THIS INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 21449, WPPSS NUCLEAR PROJECT 2 SECOND/RY CONTAINMENT OVERPRESSURIZATION POTENTIAL DRAINING OF SUPPRESSION POOL BRUNSWICK 1 8 2 MULTIPLE PROBLEMS AT BRUNSWICK STATION INDIAN POINT 2 POTENTIAL COMMON MODE FAILURE OF SERVICE WATER SYSTEM

WPPSS NUCLEAR PROJECT 2 SECONDARY CONTAINMENT OVERPRESSURIZATION FEBRUARY 15, 1988 PROBLEM DURING BREAKER TESTING, THE REACTOR B'ILDING U SUPPLY FAN WAS INADVERTENTLY STARTED WITH ITS ASSOCIATED TRIP CIRCUITRY DE-ENERGIZED, THUS OVERPRESSURIZING CONTAINMENT TO THE POINT OF FAILURE BEFORE THE FAN WAS LOCALLY TRIPPED.

CAUSE INSTALLATION DEFECTS AND PERSONNEL ERRORS CONTRIBUTED TO EVENT, o LOOSE FUSE CLIP PREVENTED TRIP CIRCUIT FROM BEING ENERGIZED o AN "A" CONTACT (0FF THE FEEDER BREAKER SUPPLYING THE IB FAN) WAS WIRED OUT OF THE CIRCUIT CAUSING THE SUPPLY FAN TO AUTO START WHEN TAKEN OUT OF THE PULL-T0-LOCK, o EQUIPMENT OPERATOR AND CONTROL ROOM OPERATOR HAD NO INDICATION OF FAN STATUS NEVERTHELESS CONTINUED WITH THE EVOLUTION ANYWAY, SIGNIFICANCE o FAILURE IN NON-SAFETY HVAC COULD COMPROMISE SECONDARY CONTAINMENT INTEGRITY, o SECONDARY CONTAINMENT MAY HAVE FAILED AT LESS THAN ITS DESIGN PRESSURE, o REPAIR EVOLUTION, GRANTED 48 HOUR EMERGENCY T.S. RELIEF, DISCUSSION o WHILE SHUTDOWN TO PLUG SEVERED CONDENSER TUBE, WNP-2 WAS CONDUCTING SHORT TERM INSPECTION OF WESTINGHOUSE CIRCUIT BREAKER (PER NRC BULLETIN 88-01),

o COMPLETED INSPECTION OF 480V BREAKER FOR THE REACTOR BUILDING SUPPLY FAN AND WAS RETURNING FOR SERVICE.

EQUIPMENT OPERATOR REINSTALLED 2 FUSE BLOCKS BUT FAILED TO NOTICE LACK 0F LOCAL BREAKER POSITION INDICATION, CONTACT: L, ZERR

REFERENCE:

ERN 11508, DR 02/16/88, DR 02/19/88, PNO-V-88-13

CONTROL ROOM OPERATOR OBSERVED NO INDICATION BUT TOOK THE SWITCH OUT OF PULL-TO-LOCK ANYWAY, HE THEN REPLACED THE LIGHT BULB, BUT STILL HAD NO INDICATION (POWERED OFF TRIP CIRCUITRY)),

CONTROL ROOM SUPERVISOR AND OPERATOR SAW THAT D/P (BETWEEN OUTSIDE AND CONTAINMENT) PEGGED THE METER AT 6,5" 0F WATER AND THEN DROPPED OFF TO 1,5", DISPATCHED EQUIPMENT OPERATOR TO LOCALLY TRIP FAN,

- FAN RAN FOR NINE MINUTES BEFORE TRIPPED, BOTH FUSE BLOCKS WERE REPLACED, LOOSE CLIP WAS NOT FIXED, BUT AFTER INSTALLATION THEY HAD INDICATION, CONTROL ROOM OPERATOR THEN TOOK FAN SWITCH OUT OF THE PULL-TO-LOCK POSITION AND THE FAN AUTO STARTED AGAIN, HE THEN STARTED THE EXHAUST FAN, ONCOMING EQUIPMENT OPERATOR NOTICED NUMEROUS NUTS AND BOLTS ON THE REFUELING FLOOR APPR0XIMATELY 2 HOURS LATER.

- ONE HOUR LATER SECONDARY CONTAINMENT WAS DECLARED IN0PERABLE, OPENING IS 18" BY 30 FEET, OTHER INTERESTING ITEMS o FAN RAN FOR APPR0XIMATELY 2 MINUTES BEFORE THE SHEARING BOLTS SHEARED (DESIGNED TO SHEAR AT .5 PSI OR APPR0XIMATELY 14" 0F H 0), j 2

o B CHANNEL WHICH POWERS THE B FAN TRIP CIRCUITRY HAD A MISSING l WIRE WHICH WOULD HAVE PREVENTED THE TRIP IF THE FANS HAD BEEN REVERSED, o HAD SIMILAR PROBLEM IN THE PAST AND A WORK REQUEST WAS SUBMITTED TO TROUBLESHOOT THE PROBLEM BUT NEVER CARRIED THROUGH TO THE DEGREE NECESSARY TO FIND THE ROOT CAUSE,

. 1 FOLLOWUP I o REPAIR TO BE COMPLETED BY MARCH 2, 1988, o LICENSEE INVESTIGATING INSTALLATION:

- BLOW OUT PANELS ON WALLS AND/0R ROOF, ELECTRICAL INTERLOCKS BETWEEN SUPPLY AND EXHAUST FANS AND/0R l

EXHAl'ai FAN AND DISCHARGE VALVE, 0 PLANT SYSTEMS BRANCH CONCLUDED SER ON REPAIR ACTIVITY, o EAB EVALUATING GENERIC IMPLICATIONS,

WPPSS NUCLEAR PROJECT 2 POTENTIAL DRAINING 0F SUPPRESSION POOL JANUARY 16 AND FEBRUARY 19, 1988 PROBLEM LICENSEE CONCLUDED THAT A SINGLE FAILURE COULD CAUSE THE SUPPRESSION P0OL TO DRAIN THROUGH A 2" LINE, CAUSE DESIGN DEFICIENCY, DISCUSSION ,

o EARTHQUAKE CAUSES NON-SEISMIC SUCTION PIPING OF RCIC (FROM THE CST) TO FAIL, o RCIC SUCTION VALVE (RCIC-V-10) FAILS TO CLOSE, o FLOW PATH EXISTS VIA THE KEEP-FILL PUMP SUCTION LINE WHICH COULD DRAIN THE SUPPRESSION P0OL (KEEP-FILL PUMP BYPASSES RCIC SUCTION CHECK VALVE),

o MANUAL OPERATOR ACTION TO CLOSE RCIC-V-31, o LICENSEE IMMEDIATE ACTION WAS TO ALIGN RCIC SUCTION TO THE SUPPRESSION P0OL, '

o PART 21 TO BE FILED, o CHECK VALVE MAY BE INSTALLED UPSTREAM 0F RCIC-V-10, FOLLOWUP EAB IS ASSESSING GENERIC IMPLICATIONS, I

i l l

l CONTACT: L. ZERR  !

REFERENCES:

ERNS 11296 AND 11341, DRs 01/26/88 AND 02/19/88,

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3RUNSWICK 1 & 2 MULTIPLE PROBLEMS AT BRUNSWICK STATION FEBRUARY 1988 PRORLEMS

1. BY 50,72 REPORT 11419, DATED FEBRUARY 2, 1988, THE LICENSEE NOTIFIED THE STAFF 0F A HYDR 0 GEN CONCENTRATION GREATER THAN THE FLAMMABLE LIMIT IN THE UNIT ONE TURBINE BUILDING.

HYDR 0 GEN RELEASED FROM A NEWLY INSTALLED VALVE WHICH WAS NOT TESTED PRIOR TO BEING PLACED INTO SERVICE. THE REACTOR AND TURBINE BUILDING WAS EVACUATED AND THE HYDR 0 GEN SUPPLY ISOLATED,

2. IN THE FEBRUARY 16 MORNING REPORT, THE LICENSEE NOTIFIED US THAT A NITROGEN INERTING LINE HAD FAILED, AS A RESULT, SAND COVERING THE LINE, HAD BEEN INTRODUCED INTO BOTH TORUS OF BOTH UNITS AND TORUS VACUUM BREAKERS OF UNIT 2. SINCE THEN THE NITROGEN LINE HAS BEEN CLEANED OUT AND REPAIRED AND SAND REMOVED FROM BOTH UNITS. THE VACUUM VALVES HAVE BEEN TESTED SATISFACTORILY,

3. BY 50,72 REPORT 11514 DATED FEBRUARY 19, 1988 THE LICENSEE NOTIFIED THE STAFF 0F MANY FAILED BOLTS IN VITAL DC SYSTEMS AND A FEW IN THE AC SYSTEMS AS INDICATED BY SEVERE CRACKING NEAR THE BOLT HEADS. THE FAILURES IN THE AC SYSTEMS ARE  ;

BELIEVED TO BE RAND 0M. THE FAILURES IN DC SYSTEMS ARE DUE TO OVERT 0RQUING AT TIME OF CONSTRUCTION, ALL SUCH BOLTS WERE OVEPT0RQUED DUE TO WRONG TOROVE VALUES SUPPLIED BY GENERAL ELECTRIC, THE ERROR WAS DETECTED BY GE AND CP8L WAS NOTIFIED PRIOR TO STARTUP, THE BOLTS WERE REPLACED IN THE AC SYSTEMS, BUT, FOR AN UNKNOWN REASON, THE DC SYSTEMS WERE NOT REPAIRED, l

GENERAL ELECTRIC IS REVIEWING ITS RECORDS TO DETERMINE IF ANY OTHER NUCLEAR PLANTS ARE INVOLVED, CONTACT: R, SCHOLL

REFERENCES:

DR 02/16/88 AND ERN 11545 l

INDIAN POINT 2 POTENTIAL COMMON MODE FAILURE OF SERVICE WATER SYSTEM PROBLEM POTENTI AL COMMON MODE FAILURE OF SERVICE WATER- PUMPS DUE TO ENERGETIC FAILURE OF THE ASSOCIATED POWER CABLING.

C.AUSE DEGRADATION DUE TO WATER INTRUSICN IN CABLE SPLICES.

SAFETY SIGNIFICANCE ,

POTENTIAL LOSS OF ULTIMATE HEAT SINK.

DISCUSSION o RECENT SAFETY SYSTEM FUNCTIONAL INSPECTION IDENTIFIED POTENTIAL COMMON MODE FAILURE.

o ALL SERVICE WATER PUMP POWER CABLES RUN FROM PLANT SWITCHGEAR TO ALL SIX PUMPS THROUGH ONE MANHOLE.

o CABLES SPLICED IN ONE MANHOLE - ONE CONFIGURATION FOR TWO  ;

ALTERNATE SHUTDOWN PUMPS, ONE CONFIGURATION FOR FOUR REMAINING PUMPS.

o ALTERNATE SHUTDOWN PUMPS HAVE EXPERIENCED TWO ENERGETIC FAILURES SINCE 1985 DUE TO WATER INTRUSION.

o MANHOLE PARTI ALLY FILLED WITH SAND IN 1985 FOR FIRE PROTECTION.

o MANHOLE OFTEN FLOODED.

FOLLOWUP '

o THE LICENSEE IS EVALUATING. ,

o LICENSEE TO PRESENT SHORT- AND LONG-TERM CORRECTIVE ACTIONS i TO RESOLVE PROBLEM AND JUSTIFICATION FOR CONTINUED OPERATION AT MEETING AT REGION I - 02/26/88, 1

l i CONTACT: M. SLOSSON

IP-2 IP.I SwCR SwGR l l

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" - Y ARD MANHOLE NO. 21

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TRANSFER SWITCH (TYPICAL OF EDG3 l i

AND EDG4) '

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FIGURE 4.15-1 TYPICAL ARRANCEMENT-SERYlCE WATR PUMP POWER CABLES - OtE LDE l

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. ENCLOSURE 3 i

LONGTERM FOLLOWfr ASSIGNMENTS TO BE COMPLETED 1

i LONGTERM FOLLOWUPS OUTSTANDING ~

. ORGANIZATION 02/02/88 02/09/88 02/16/68 02/23/88 l EAB 2 2 2 2 EMTB 0 0 0 1 ESGB 1 1 1 1 ICSB 2 2 2 2 0GCB 1 1 1 1

, l OTSB 2 .1 1 1 PD2-2 1 1 1 1

PD2-3 1 1 1 1 PD3-2 1 1 1 1 PD3/4/5 0 0 0 1 PD5 2 2 2 1 RIII O O 1 1 RVIB 4 4 4 3  :

SELB 5 5 5 6 5 5 '!

SPLB 5 5 SRXB 2 2_ 3- 4_

! TOTAL 29 28 30 32 j i 4

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MACTOR SCRM sumMT

+ . WEEK EGING 02/21/98 4 1. PLMT SPECIFIC DATA ,

-DATE SITE JNilPONERSIGNALCAUSE COMPL1- 1TD ITD YTI  ;

CAil0NS ADOYE KLOW TOTAL

= 151 151 [

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- 02/15/SP V06TLE 1 100 A EQUIPTNT NO . 2 0 2 j d

02MelftSURRY  ! IM A PERSOMEL N0 1 0 1 +

1 100 A

'2/11/89

, S W ER EQUIPMENT NO 1 0 1 02/17/89 ARLMi45 1 80 A E90lPRENT NO '1 0 1 02/19/96 SAW OW7 kE 3 100 R UNOCM NO 1 0 1 ,

02/20!$9!! Alt 023 2 0A EDVIPPENT N3 0 1  !

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1. PLANT' SPECIFIC DATA SASEE Ch INITIAL REVIE!! 0F EC.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIONIGHT: 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 PROCECURE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.

2. COMPLICATIONSi RECOVERY COMPLICATED BY EQUlPMENT FAILURES OR PERSONNEL ERRORS UhRELATED TO CAUSE OF SCRAM.

3. PERSONNEL RELATED PROBLEMS INCLUDE 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.

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4 ENCLOSURE 4 50.72 REPORT TABULATION - 2/22/98 l

rebulation - 50.72 Reports for the cast week:

' (1). Total number of reports 48 (2) Plants in outage 15 i

(3) Plants in power ascension 5 (4) Summary of causes  ;,

DC Constr_ error or inadequacy 1 DE Design errar or inadequacy 2 DX Other des / mfg /constr inadeq 1 l HA Accidental action 2 l HP Failure to follow procedure 3 l HX Human actions, other i IC Internal to Component 5 IE Ambient env stress 1 MS Scheduled maintenance 1 FC Defective Cal /tesc proc 2 PO Defective Operations proc 1 '

U Unknown 21 No cause - info only 7 t**************************************888888*****88888888888888888888

{ 21cnt Status - 2/22/88 Plants in power ascension testing or scheduled outages, especially ofuoling, are more likely to produce more reports due to the increased activities occurring, therefore a listing of those plants in either activity is useful.  ;

A. Plants in refueling and scheduled outages during the week Arkencas 2 Ginna Oconee 2 93avar Valley i Haddam Neck Palo Verde 1 Braidwood 1 Hatch 2 Pilgrim Hope Creek Robinson 2 l Brunewick 1 t< 2  !

l otawba 2 Nine Mile Point i San Onofre 1 I I

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B. Plants in power ascension testing during the week l Braidwood 2 Fermi 2 Nine Mile Point 2 South Texas 1 l

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February 22, 1988 SECURITY EVENT

SUMMARY

for 02/15/88 through 02/21/88

================================

NSSS EVENT EVENT FACILITY VENDOR NUMBER DATE

================================

CALVERT CLIFFS 1 CE 11509 02/15/88 CLINTON 1 GE 11511 02/15/88 FT. CALHOUN 1 CE 11526 02/17/88 MCGUIRE 1 WE 11547 02/19/88 MILLSTONE 1 GE 11536 02/18/88 PALO VERDE 1 CE 11523 02/17/88 SAN ONOFRE 1 WE 11528 02/17/88 s

TROJAN 1 WE 11538 02/18/88 l

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i . j han Cades (EPoll Plaet E44ecte ute Eate n i n,

' ISvolge/Hg/Constrleadequacy BM Systees, etelpeset, l 3 Plantsee'atiana  !

andler strettures feend 94 Plant W inition set to be designed, tadiological controls hequirpesets !eafetuuy eseafattured, a actuentienal rad safety K Besign Error er inadequacy toestretted,orlastelled j i

t rad ente ungeant BM Mg Error er leadequacy la accordance eith K Constr Error w Inadequay approved pleet design eradeffletetcontrali ' f esentrieg 31 Other soutfirstions.

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