ML20150D717

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Summary of Operating Reactors Events Meeting 88-26 on 880628
ML20150D717
Person / Time
Site: Salem, Perry, Crystal River, 05000000
Issue date: 07/07/1988
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-88-026, OREM-88-26, OREM-YY-XXX, NUDOCS 8807140114
Download: ML20150D717 (17)


Text

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JUL 7 28 MEMORAllDUM 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

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING June 28, 1988 - MEETING 88 26 On June 28, 1988 an Operating Reactors Events meeting (88 26) was held to brief senior managers from NRR, OSP, AE00, Regional Offices, and Commission staff on events which occurred since our last meeting on June 21, 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. Enclosure 3 presents one event suggested for long-term followup and a summary of reactor scrams. Three significant events were identified for input to fiRC's performance indicator program.

Wayne Lanning, Chief Events Assessment Branch Division of Operationai Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/Encio.:

See flext Page DISTRIBUTION A( g Centra l . F ile 1 EAB Reading File Circulating Copy EAB Staff

. [if'j / g-p g(p MLReardon, EAB 9a 00udinot, EAB /, Y jM~

LKilgore, SECY, POR l

C:E  :  :  :

OFC EAB t R NRR  :  :

NAME :MLReardon :W g'  :  :  :  :  :

DATE :07/45 /88 :07/ /88  :  :  :  :

0FFICIAL RECORD COPY 8807140114 e80707 PDR ADOCK 05000302 S PNU

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>T.-surley,12G-18 J. Forsyth, INPO j F. Miraglia, 12G-18 E. Jordan, AEOD T. Colburn, 13E-11 E. BecLjord, NL-007 K. Perkins, 13E-19 W. Russell, RI H. Silver, 14H-22 l I

B. Davis, Rlll H. Berkow, 14H-20 J. Nelson Grace, Ril D. Fischer, 14E-21 R. D. Martin, RIV W. Butler, 14E-21 J. B. Martin, RV W. Kane, RI L. Reyes, Ril E. Greenm'an. Rill J. Callan, RIV D. Kirsch, RV l

S. Varga, 14E-4 D. Crutchfield, 13A-2 B. Boger, 14A-2 l G. Lainas, 14H-3

( G. Holahan, 13E-4 L.'Shao, 8E-2 J. Partlow, 7D-24 B. Grimes, 9A-2 l F. Congel, 10E-4 E. Weiss, AE0D S. Black, 12E-4 I

T. Martin, 12G-18 '

J. Stone, 9D-4 R. Hernan, 13H-3 H. Bailey, AE0D l

.J. Guttraann, SECY

' A. Thadani, 7E-4

5. Rubin, AE0D R. Barrett, 10E-2 M. Harper, EWS-263

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-26)

June 28, 1988 NAME ORGANIZATION NAME ORGANIZATION W.R. Butler NRR/PD1-1 A. Thadani NRR/ DEST B.A. Boger NRR/ADR1 P. Baranowsky NRR/DOEA D.C. Fischer NRR/DOEA W.'Lanning NRR/COEA C.E. Rossi NRR/DOEA' D. Crutchtleid NRR/DRSP C. Schulten NRR/00EA W. Minners RES/DRPS M.C. Reardon NRR/00EA W.H. Regan NRR/DLPQ E.A. Reeves NRR/PD2-1 C.J. Haughney NRR/DRIS H. Silver NRR/PD2-2 S.D. Ruben AEOD/D0A H.B. Clayton OE00 0.H. Moran OSP/TVA V. Benaroya AE0D/DSP T. Colburn NRR/PD3-3

5. Varga NRR/DRP H. Berkow NRR/PD2-2 E.G. Adensam NRR/DRP M. Callahan GPA/CA D.C. Fischer NRR/DRP L. Olshan NRR/DRSP J

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ENCLOSURE 2

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OPERATING REACTORS EVENTS BRIEFING 88-2G EVENTS ASSESSMENT BRANCH LOCATION: 12-B-11 WHITE FLINT IDESDAY, JUNE 28, 1988, 11:00 A.M.

TIHANGE UNIT 1 ECCS PIPING CRACKS CRYSTAL RIVER UNIT 3 CHECK VALVE LEAK IN AUXILIARY FEEDWATER SYSTEM SALEM UNIT 2 LOSS OF VITAL 120 VAC INSTRUMENT BUS AND INVERTER PERRY UNIT 1 PERRY SCRAMS

88-26 TlHANGE UNIT 1 ECCS PIPING CRACKS JUNE 18, 1988 PROBLEM CRACKS IN ,AN UNIS0LABLE ECCS PIPE CONNECTED TO THE RCS HOT LEG.

CAUSE UNKNOWN. .

SAFETY SIGNIFICANCE CIRCUMFERENTIAL FAILURE OF THE LlHE WOULD RESULT IN A 6-INCH LOCA.

DISCUSSION o THE UNIT IS AN 870 MWE, M-TYPE, 3-LOOP PWR IN BELGIUM.

o WHILE CPERATING, A SUDDEN LEAK OCCURRED.

o RADI0 ACTIVITY AND HUMIDITY IN CONTAINMENT INCREASED AND VCT WATER LEVEL DECREASED.

o THE LEAK RATE WAS 6 GPM.

O CRACKS WERE FOUND BY UT AND RT AS SHOWN IN THE ATTACHED DIAGRAM, o NO CRACKS HAVE BEEN FOUND IN SIMILAR PIPING CONNECTED TO THE OTHER 2 HOT LEGS AND TO THE 3 COLD LEGS.

o THIS EVENT IS SIMILAR TO THE FARLEY 2 EVENT OF 12/09/87 EXCEPT:

FARLEY HAD ONE CRACK AND THAT WAS IN THE ECCS LINE CONNECTED TO A COLD LEG.

THE FARLEY CRACK WAS IN A WELD AND THE HEAT AFFECTED ZONE.

THE FARLEY CRACK OCCURRED SI.0WLY.

o AFTER THE FARLEY EVENT, INFORMAT10h NOTICE 88-01 WAS ISSUED ON 01/28/88 AND BULLETIN 88-08 WAS ISSUED ON 06/22/88.

FOLLOWUP o THE BELGIANS:

ARE EXECUTING BULLETIN 88-06.

WILL PROVIDE NRC WITH A REPORT OF THEIR FINDINGS THIS WEEK.

o OEAB HAS PREPARED SUPPLEMENT 1 TO BULLETIN 88-08 TO EMPHASlZE THE NEED FOR ADDRESSEES TO EXAMINE BASE METAL, CONTACT: R. WOODRUFF

REFERENCE:

TELECON 06/21/88

A - TilROUGil-WALL CRACK, 3.5 ItOES Loto INSIDE,1.6 ItOES [OtU OUTSIDE B - CRACK INDICATION, 3.9 ItOE IDNG .

INSIDE, 100 MILS DEEP C "IHO SMALLER INDICATIONS IN 'IEE VICINITY OF TIE WELD CIIECK VALVE i

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88-2G CRYSTAL RIVER UNIT 3 CHECK VALVE LEAK IN AUXILIARY FEEDWATER SYSTEM JUNE 21, 1988 i

PROBLEM

[ STEAM LEAKING INTO EllERGENCY FEEDWATER (EFW) SYSTEM PIPING, CAUSE LEAKING VALVE BONNET AND BACK LEAKAGE THROUGH CHECK VALVE, SAFETY SIGNIFICANCE POSSIBILITY OF EXCESSIVE THERMAL STRESSES IN EFW PIPING, SUPPORTS AhD CONTAINMENT PENETRATION, POSSIBILITY OF WATER HAMMER ON EFW ACTUATION, 1

DISCUSSION o CRYSTAL RIVER IS IN A TWO YEAR FUEL CYCLE WHICH BEGAN LAST FALL.

o IN JANUARY 1986 THE VALVE BONNET OF EFV-18 SEGAN TO LEAX,

! o EFV-43 HAS HAD A HISTORY OF BACK LEAKAGE PROBLEMS, o THE LICENSEE TOUCH TESTED EFW PlPING EACH SHIFT IN ACCORDANCE

! WITH IE BULLETIN 85-01, o TEMPERATURE INCREASE IN EFW PIPING WAS OBSERVED IN MAY 1988, I o BY JUNE 21, 1988 THE BONNET LEAK 0F EFV-18 HAD CHANGED TO STEAM, o PIPING DOWNSTREAM 0F EFV-38 REACHED 400*F - DESIGN IS 110*F.

i. O PIPING UPSTREAM OF EFV-18 AT AMBIENT INDICATING NO EFV-18 SEAT LEAKAGE, l 0 ONE EFW PIPE ANCHOR FOUND PULLED LOOSE HAS BEEN REPAlRED.

o LICENSEE EVALUATING POSSIBLE TilERMAL DAMAGE TO EFW PIPING, ANCHORS AND PENETRATION - NONE BELIEVED TO HAVE OCCURRED BY LICENSEE, o STAFF CONCERN WITH POSSIBLE WATER HAMMER.

f o TEMPORARY FIX OF PbMPING WATER INTO AFFECTED PIPING WAS EFFECTIVE l IN LOWERING THE TEMPERATURE BELOW 110*F.

r CONTACT: W. JENSEN

REFERENCE:

50.72 # 12605 AND MORNING REPORT 06/23/88

. CRYSTAL RIVER 3 2-FOLLOWUP o LICENSEE WISilES TO DELAY FIX OF EFV-18 AND EFV-43 UNTIL NOVEMBER

.1989 REFUELING, EXTENT AND SCHEDULE OF REQUIRED REPAIRS UNDER DISCUSSION.

o o NRR-TO. ISSUE 50,54(F) LETTER.

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CRYSTAL RIVER UNIT 3 V EMERGENCY FEEDWATER SYSTEM t

88-2G SALEM UNIT 2 LOSS OF VITAL 120 VAC INSTRUMENT BUS AND INVERTER JUNE 22, 1988 PROBLEM LOSS OF THE "2C" VITAL INVERTER BUS CONNECTED TO THE "2C" VITAL

. INSTRUMENT BUS RESULTED IN A REACTOR SCRAM AND SI.

CAUSE ,

LOSS OF THE VITAL INVERTER WAS CAUSED BY A MALFUNCTION IN THE INVERTER'S MASTER FIRING CIRCUIT (A NUMBER OF FUSES WERE BLOWN),

SAFETY SIGNIFICANCE EVENTS INVOLVING VITAL INVERTER FAILURES OFTEN INVOLVE BUS FAILURES, RESULTING IN PLANT SCRAMS AND CHALLENGES TO SAFETY SYSTEMS.

DISCUSSION o JUNE 22, 1988, SALEM UNIT 2 EXPERIENCED A SCRAM FROM 100% POWER DUE TO THE LOW RCP Fl0W TRIP SIGNAL PRESENT.

o THE TRIP SIGNAL RESULTED DUE TO LOSS OF THE VITAL INVERTER SIMULATING THE POSITION OF THE RCP "2B" BREAKER AS "0 PEN".

0 THIS CIRCulTRY DESIGN APPEARS 10 BE LIMITED TO OLDER DESIGNS ON WESTINGHOUSE PLANTS. FOR THIS LICENSEE, AB0VE 36% POWER, A 1 0F 1

-LOGIC WILL GENERATE AN R x TRIP SIGNAL ON LOW REACTOR COOLANT LOOP FLOW.

o SI WAS INITIATED DUE TO:

1. TWO CHANNELS OF LOW STEAM LINE PRESSURE FAILED DUE TO FAILURE OF THE ASSOCIATED INVERTER (2/4 LOGIC ACTUATION).

2, 2/4 HIGH STEAM FLOW - CAUSE WAS HIGH STEAM FLON SIGNAL GENERATED DUE TO TRIP TRANSIENT (SETPOINT VARIABLE ON Rx POWER).

o PLANT PRIMARY SIDE WENT SOLID (AS A RESULT OF SI), PORV's LIFTED, RESEATED..

o PEAK PRIMARY PRESSURE REACHED WAS 2395 PSI (PORV SETPOINT - 2335, PZR SAFETY VALVE - 2485).

o RCS TEMP. DID NOT REACH L-TAVG SETPOINT.

CONTACT: J. THOMPSON

REFERENCE:

50.72 # 12G18 AND MORNING REPORT 06/23/S8

SALEM UNIT 2 .

o PZR CODE SAFETIES DID NOT LIFT, o SECONDARY PORVs ACTUATED, o OPERATORS FOLLOWED THEIR E0P PROCEDURES AND THE PLANT RESPONDED AS EXPECTED.

o S1 WAS TERMINATED 24 MIN. INTO THE EVENT, o THIS EVENT WAS SIMILAR TO THE AUGUST 198G EVENT (SAME INVERTER FAILURE.,DUE TO PERSONNEL ERROR),

FOLLOWUP o THE LICENSEE HAS REPAIRED THE INVERTER AND THE UNIT IS BACK IN POWER OPERATIONS, o Tile LICENSEE IS PERFORMING A POST-TRIP REVIEW 0F THIS EVENT ALONG WITH REVIEWING THE ADEQUACY OF THEIR E0Ps, o EAB IS STILL EVALUATING LICENSEE'S RESPONSE TO THIS EVENT,

88-26

-PERRY SCRAMS april 28, 1988 THRU JUNE 23, 1988 CAUSE RAIE POWER LEVEL EQUIPMENT F,.iLURE 06/23/88 84%

TURLINE-TRIP.

-EQUIPMENT PROBLEM 06/16/88 100%

HIGH NEUTRON FLUX WHILE TROUBLESHOOTING FLOW CONTROLLER, PERSONNEL ERROR DURING POWER TRANSIENT, 06/08/88 24%

DE-ENERGlZED 2 0F 3 NONSAFETY BUSES, PERSONNEL ERROR DURING POWER INCREASE, U6/05/88 80%

INADVERTENT SWITCH TO AUTO FLUX, EQUIPMENT FUSE BLOWN DURING SURVEILLANCE, U5/06/88 100%

1/4 0F RODS INSERTED, PROCEDURE DEFICIENCY 04/30/S8 2%

DNEXPECTED BYPASS VALVE OPENING DURING STARTUP, PERSONNEL ERROR FOLLOWING SURVEILLANCE. 04/28/88 100%

EUS INADVERTANTLY DE-ENERGlZED, CONTACT: J. CARTER

REFERENCE:

50.72 # 12623, 12570, 12498, 12466, 12214, 12166, AND 12136

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SUMMARY

WCEK ENDING 06/26/88

1. PLANT SPECIFIC DATA DATE $1TE UN!? POWER 516kAL CAUSE COMPLI- YTD YTD YiB CATIONS A80VE BELOW TOTAL 151 151 06/20/88MCSUIRE 1 100 A E M PMENT NO 4 0 4 06/20/88 CATAWBA 2 85 M EQUIPMENT NO 5 1 6 06/20/88 BRAIDWOOD 2 49 A EGulPMENT N3 1 2 3 06/21/68 BRAIDWD0D 2 3A PERS0hhEL NO 1 3 4 06/22/88 BR4!CWOOD 2 25 A PERS0hNEL M 2 3 5 06/22/88 NINE MILE POINT 2 98 A EQUIPMENT h3 5 0 5 06/22/98 SALEM 2 100 A E30!PPENT W3 3 1 4 05/23/88 FERRY 1 84 A E3UIPMENT NO 4 3 7 06124/98 BRAltt00D 2 21 A E3UlF3E47 N3 3 3 6

, 06/24/88 VERMCNT YANKEE A 100 A E301FFENT h3 1 0 1 06/25/98 CLINICN I 0A EGUIFrENT C 0 1 1 i

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 06/26/88 POWER NUMBER 1988 1987 1986 1985 SCRAM CAUSE WEEKLY WEEKLY OF WEEKLY WEEKLY s

's AVERAGE AVERAGE AVERAGE AVERAGE SCRAMS (5)

YTD .(3)(4) (B)(9)

    • POWER >15% 2.8 3.9 4.3 5.4 EQUIP. RELATED >15% 8 1 1.0 1.3 1.8 2.0 PERS. RELATED(6) >15% 0.9 1.2 0.4 0.6 OTHER(7) >15% 0
    • Subtotal ** 6.4 6.5 8.0 9 4.7
    • POWER <15% 1.2 1.4 1.3

<15% 1 0.7 EQUIP. RELATED 0.6 0.6 0.8 0.9 '.'

<15% 1 PERS. RELATED 0.3 0.2 0.2

<15% 0 0.3 .,

OTHER .

    • Subtotal ** 2.1 2.4 2.4 2 1.6
      • Total *** 8.5 0.9 10.4 11 6.3 MANUAL VS AUTO SCRAMS NUMBER 1988 1987 1986 1985 .

TYPE WEEKLY WEEKLY OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE YTD 1 1.1 1.4 1.0 1.0 MANUAL SCRAMS 7.9 9.4 10 5.2 7.0 AUTOMATIC SCRAMS t

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1. FUf4T SFECIFIC DATA BAEED CN INITIAL FEVIEW 7 50.72 FEFCETS l

FCR T}E kEEX CF INTEFEST. FERICD IS MIDNIGir SLNDAY TW41.Gi

  • MIDNIGHT: SLtOAY SCF#6 ffE DEFItED AS FEfCr[R Fhutta iIW (CTUATIQ6 L44ICH FESLLT IN ROD tOTICN, AND EXCLIIE FUMED TESTS CR EDWS AS F%7 CF FUNED EHJTDG44 IN ACCCRIWG WITH A FUNT FEOCEDLFE. THEFE ffE 1C6 FEACTORS Hl.DItG (W CFEPATItG LICENEE.
2. CaFLIL'ATICN3: FECCMERY CDfLICATED BY ECUIFtENT FAILLFES CR FERSGtEL EFECFS LtFEl.ATED TO CAGE CF ERft1.
3. FEFSCNEL FEl ATED FEDELDS It4'LUEE H.NN ETSCR, FEOCEDLEAL DEFICIEM:IES, fND MW.YL STEffi CDERATCR LEVEL CCNTFCL FEDEtB S. ,

L 4. "0THER" IPELUDES FUTCt% TIC SCT#S ATTRIEUTED TO ENJIFOtENT/L C/UEES (LICHTNItG), SYSTEM DESIG4, CR Litt044 CFLEE.

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