ML20043E431

Summary of Operating Reactors Events Meeting 90-13 on 900523.List of Attendees & Significant Elements of Discussed Events Encl

ML20043E431
Person / Time
Site:	Oconee, Brunswick, Surry, Haddam Neck, Clinton  File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/25/1990
From:	Fischer D Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-90-013, OREM-90-13, OREM-YY-XXX, NUDOCS 9006120436
Download: ML20043E431 (19)

Text

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't May 25,1990 MEMORANDUM FOR:

Charles E. Rossi, Dirertor Division of Operationa? Events Assessment E

FROM:

. David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE.0PERATING REACTORS EVENTS-MEETING.

May 23, 1990 - MEETING 90-13 t

On May 23,.1990, weconductedanOperatingReactorsEventsmeeting(90-3) to inform senior managers from NRR, ACRS, Commission staff, and regional offices of selected events that occurred since our last briefing on May 16, 1990. lists the attendees. presents the significant elements of the discussed events. contains' reactor scram statistics for the week ending 05/20/90..

No significant events were-identified for input into the NRC performance indicator program.

Original signed by David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment L

Enclosures:

As stated cc w/ Encl..-

-See Next Page t

T STRIBUTION

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-CC' T. Murley, NRR E.-Tourigny, NRP.

F._Miraglia, NRR

_E. Adensam,.NRR

'W.Russell, NRR J. Nickman, NRR

-J. Partlow, NRR J. Craig, NRR S. Varga,LNRR J. Stolz, NRR B._Boger, NRR A. Wang, NRR G. Lainas -NRR.

L. Wiens, NRR F. Congel, NRR D. Matthews, NRR A.-Thadani, NRR B. Buckley, NRR J. Richardson, NRR H. Berkow, NRR R.- Barrett,;NRR

,J. Roe, NRR

.T. Martin, RI-W. Kane, RI-S.' Ebneter, Ril L. Reyes, Ril B. Davis, Rlll E. Greenman, Rlli S, Collins, ~RIV R.D. Martin, RIV

-J.B.. Martin, RV

'R. Zimmerman, RV P. Boehnert ACRS-E. Weiss, AE00 S. Rubin, AE0D M. Harper, AE00 J. Taylor,'EDO J. Dyer,- EDO~

R. Newlin, GPA

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-J. Cowan,.-INP0 E. Beckjord RES A. Bates, SECY s-

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~ L' ENCLOSURE'1 i

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LIST.0F ATTENDEES OPERATING REACTCRS. EVENTS. BRIEFING.(90-13)

-May 23, 1990 NAME ORGANIZATION NAME

' ORGANIZATION l

C. Rossi NRR/DOEA B. Grines NRR/DRIS'

'P. Boehnert ACRS P. Baranowsky HRR/DOEA M.'Reardon NRR/DOEA M. Case NRR/DLPQ A. Mattson NRR/DOEA J. Donohew NRR/ADSP i

G._Hubbard.

NRR/SPLB A. Wang-NRR/PD1-4 R.' Woodruff NRR/DOEA J. Stolz NRR/PD1-4 D. Fischer NRR/DOEA J. Thompson NRR/DOEA L. Reyes R11 K. Eccleston NRR/DRP C.. Sellers NRR/EMCB W. LeFave NRR/ DST J. Richardson NRR/DET J. Scarborough OCM/KR L. Wiens NRR/PD2-3 W. Troskoski OE I

D. Trimble OCM/JC M. Slosson OEDO L

B. Wetzel NRR/DLPQ K. Perkins NRR/LOLB

D' Lange NRR/DLPQ A. Young NRR/D0EA

-C. Thomas NRR/DLPQ G. Lainas NRR/DRP-

.D.-Matthews NRR/DRP-E. Adensam NRR/DRP R._ Benedict NRR/D0EA L. Kintner NRR/PD2-1 l '

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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 90-13 I

EVENTS ASSESSMENT BRANCH

+

LOCATION:

12B-11, WHITE FLINT q

WEDNESDAY, MAY 23, 1990, 11:00 A.M.

l CLINTON UNIT 1 MISPOSITIONED SERVICE WATER VALVES CAUSE DIESEL GENERATOR INOPERABILITY

)

1 HADDAM NECK PRESSURIZER INNER SURFACE l

CRACKS l

OCONEE UNITS 1 AND 2 OVERFLOW 0F SPENT FUEL POOL l

l BRUNSWlCK UNITS'1 AND 2 FAILURE OF OPERATORS TO REQUALIFY SURRY UNITS 1 AND 2 MAIN TRANSFORMER FAULT 1

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90.

CLINTON UNIT 1 MISPOSITIONED SERVICE WATER VALVES LEAD TO DIESEL-

-GENERATOR IN0PERABillTY MAY 15,-1990 PROBLEM-DIVISION 1 AND DIVISION 11 EMERGENCY DIESEL GENERATORS (EDGs) lNOPERABLE FROM 11 MAY - 15 MAY 1990,

CAUSE

THE-THROTTLE VALVES FOR THE DIESEL GENERATOR SERVICE WATER COOLERS WERE MISPOSITIONED,

SAFETY SIGNIFICANCE P0TENTI AL FOR LOSS OR DEGRADATION OF ECCS DURING LOSS OF 0FFSITE POWER (STATION BLACK 0UT).

DISCUSSION o

FLOWsTHROUGH THE DIESEL GENERATOR SERVICE WATER COOLERS IS CONTROLLED'BY THROTTLING THE OUTLET VALVES IN EACH HEAT EXCHANGER..

o ' PROPER VALVE POSITIONS WERE ESTABLISHED DURING. SERVICE WATER FLOW BALANCING CONDUCTED DURING MARCH /APRll 1990, 0: PROPER VALVE POSITIONS WERE DETERMINED BY THE NUMBER OF TURNS-

~FROM WHERE THE VALVE LEFT ITS CLOSED. SEAT, o-RECENTLY, MAINTENANCE WAS PERFORMED ON THE SERVICE WATER EXPANSION

~ BELLOWS,

-o THE SERVICE WATER SYSTEM WAS RETURNED T0 SERVICE ON 11.MAY; HOWEVER,.

THE THROTTLE VALVES WERE POSITIONED BY COUNTING TURNS FROM THE FULLY CLOSED POSITION,

o. NO DIESEL GENERATOR OPERABILITY TEST WAS REQUIRED AFTER THIS MAINTENANCE.

-o LICENSEE ENTERED MODE 2 (STARTUP) ON 14 MAY 1990, o

ON 15 MAY, DURING EDG SURVEILLANCE, THE DIVISION 1 EDG TRIPPED ON HIGH COOLING WATER TEMPERATURE AFTER RUNNING FOR FIVE MINUTES, l

CONTACT:

A MATTSON SIGEVENT:

YES

REFERENCES:

10 CFR 50,72# 18488 AND MORNING REPORT 05/16/90

=i;

4:

CL1,NTON UN1T 1-90-13 DISCUSSION (CONTINUED)-

0 'llCENSEE FOUND DIVISION 11 EDG COOLING WATER IN THE SAME 1

CONDITION,

-o ALMOST ALL TRIPS FOR THE EDGs (AFTER RECEIVING A VAllD START SIGNAL) ARE BLOCKED WHILE IN MODE 1, 2, OR 3.

FOLLOWUP-0 LICENSEE PLANS ON MAKING SOME SORT-0F POSITIVE POSITION INDICATION FOR ALL SERVICE WATER SYSTEM VALVES (E.G. A MARK ON THE STEM-AT THE CORRECT POSITION),

o REGION IS PLANNING TO USE THIS AS FURTHER JUSTIFICATION FOR ESCALATED ENFORCEMENT BASED ON SERVICE WATER PROBLEMS AT CLINTON, o

N0.FURTHER EAB. ACTION IS REQUIRED, I

90-13 HADDAM NECK PRESSURIZER INNER SURFACE CRACKS-MAY 16, 1990 PROBLEM CRACKS INSIDE PRESSURIZER; POTENTIAL CRACKS IN BASE METAL CAUSE-UNDER-INVESTIGATION SAFETY SIGNIFICANCE POTENTIAL DEGRADATION OF REACTOR COOLANT PRESSURE B0UNDARY DISCUSSION o

THE CURRENT REFUELING OUTAGE SINCE FEBRUARY 1990, HAS BEEN DEVOTED TO CLEAN-UP 0F RCS DEBRIS, FLAKES OF DEBRIS HAD CAUSED FUEL DAMAGE DUE TO IMPINGEMENT, CLEAN-UP EFFORTS INCLUDED DACKFLUSH AND INSPECTION OF RCS, INCLUDING THE PRESSURIZER, o. CAMERA EXAMINATIONS OF THE PZR INTERNALS.AND UT EXAMINATIONS REVEALED CRACK INDICATIONS IN THE CLAD AND POTENTIAL CRACK INDICATIONS IN THE BASE METAL, o

NO FLAKES-0F DEBRIS WERE FOUND INSIDE THr PZR.-

o CLAD INDICATIONS APPEAR TO SPAN CIRCUMFERENTIALLY ALONG THE LENGTH OF THE CYLINDER,.

i o

THERE IS SOME EVIDENCE OF RUST, FOLLOWUP-0-

LICENSEE IS PLANNING TO PERFORM RADIOGRAPHY TO CONFIRM UT

' CRACK-INDICATIONS, o

NRR AND REGION ARE FOLLOWING LICENSEE'S ArTIVITIES, o

LICENSEE IS CONSIDERING PRZ RELACEMENT,

~ CONTACT:' A, YOUNG SIGEVENT:

TBD

REFERENCE:

MORNING REPORT 05/16/90 1.

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90-13 OCONEE UNITS l AND-2

'0VERFLOW 0F SPENT FUEL POOL i

MAY 17, 1990

^

PROBLEM-l SPENT FUEL POOL OVERFLOWED, SENDING 5000 GALLONS OF WATER INTO OTHER AUXILIARY BUILDING ROOMS, 3

CAUSE l

LOPERATOR CLOSED VALVES BETWEEN SPENT FUEL POOL AND REACTOR BUILDING

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' TRANSFER CANAL, SPENT FUEL PUMPS CONTINUED TO PUMP WATER FROM TRANSFER CANAL TO SPENT FUEL POOL (SFP), FILLING AND DVERFLOWING THE POOL, SAFETY SIGNIFICANCE NORMALLY UNCONTAMINATED AREAS OF AUXILIARY BUILDING AND GROUND OUTSIDE BECAME CONTAMINATED, N0 AIRBORNE CONTAMINATION AND NO CONTAMINATION OulSIDE THE SECURITY FENCE.

DISCUSSION

^

o -DVRING REFUELING, SFP PUMPS "A" AND "C" RECIRCULATE POOL WATER

ONLY, PUMP "B" CIRCULATES-P0OL WATER THROUGH TRANSFER CANAL AND BACK TO P0OL, i

o NORMALLY AFTER REFUELING, ALL PUMPS ARE STOPPED, -THEN VALVES ARE REALIGNED TO DRAIN TRANSFER CANAL TO B0 RATED WATER STORAGE TANK (BWST), BUT MAINTAIN COOLING 0F SFP WATER, o- 0PERATOR ERROR:

CLOSED TRANSFER TUBE VALVES SF 1 AND 2 WITHOUT

' STOPPING PUMPS, PUMP "B" BEGINS TO DRAIN CANAL TO SFP RATHER THAN BWST, o

EARLIER, SFP-LEVEL GAUGE PEGGED HIGH DUE TO PRESSURE INCREASE IN REACTOR BUILDING, LOCKING-IN THE HIGH LEVEL ALARM, o

ABOUT 35 MINUTES AFTER VALVE' ERROR, WATER NOTICED IN THE LOW PRESSURE INJECTION ROOM, THEN IN THE KITCHEN.

SFP OBSERVED TO

'BE OVERFLOWING, PUMPS WERE STOPPED, THEN PUMP "A" RESTARTED, CONTACT:

R. BENEDICT SIGEVENT:

NO

REFERENCE:

10 CRF 50.72# 18502 a.

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5 0,CONEE UNITS 1 AND 2 90-13 DISCUSSION!(CONTINUED) o WATER OBSERVED IN:

REAR OF CONTROL ROOM CABLE ROOM

-HOT MACHINE SHOP

-PENETRATION ROOMS LOW PRESSURE INJECTION ROOM YARD AREA (8 - 10 FT2 GRAVEL REMOVED, BLACKTOP OK),

o IMMEDIATE ACTION COVER STORM DRAIN-PUT ABSORBENT MATERIAL ON YARD WATER o

LATER ACTION (1/2 HOUR)

AFTER CLEARING RED TAG ON VALVE SF 1, OPENED VALVE LOCALLY TO DECREASE POOL LEVEL, RADIATION ~ AREAS IDENTIFIED AND R0 PED OFF SPILLS COVERED, PLASTIC OVER PANELS IN CONTROL ROOM, SMEAR AND AIRBORNE SAMPLING, SAMPLING 0F CHEMICAL TREATMENT

POND, o

1000 - 15000 DPM SURFACE CONTAMINATION, o

NO CONTAMINATION OF POND, FOLLOWUP

.o SRI' PREPARING SPECIAL REPORT ON THE EVENT, o

ALL CONTAMINATED AREAS HAVE BEEN CLEARED FOR GENERAL ACCESS.

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BRUNSWiC_KUNITS1AND2 FAILURE OF OPERATORS -T0 REQUAllFYs 1

MAY 20, 1990 PROBLEM 22 0F.47 LICENSED OPERATORS AND 7 0F.8 CREWS FAILED EITHER-THE REQUAllFICATION. EXAMINATION OR THE OPERATIONAL EVALUATION, v

CAUSE N

INADEQUATE TRAINING,

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SAFETY SIGNIFICANCE i

w FAILURE TO PERFORM AS EXPECTED COULD LEAD TO CORE DAMAGE, BACKGROUND EXAMlIIING STANDARD 601 (NUREG-1021),

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DISCUSSION

..i 0-97 SHIFT AND STAFF SR0s'-AND R0s, 1

SIMULATOR WAS MODIFIED 6 WEEKS AGO TO ALLOW o

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DRAININGcTO 150 INCHES BELOW TOPLOF ACTIVE FUEL, POWER-T0 125%,

. SATURATED ~ TEMPERATURE-AND PRESSURE TO 1140 PSIA, 1%' FUEL CLAD FAILURE (MANUALLY INSERTED),

GENERATION OF-DECAY HEAT, 4

'o REQUALIFICATION EXAMINATIONS:

SIMULATOR (TOTAL OF 9'SCENAR10S - LARGE BREAK LOCA, SMALL BREAK LOCA, ATWS, LOOP),

- -JOB PERFORMANCE MEASURES (FOCUSED WALKTHRus).

WRITTEN EXAMINATION,

~o REQUAllFICATION RESULTS:

9 0F 12 SR0s AND 5 0F 8 R0s FAILED, 3'0F 4 CREWS FAILED, CONTACT:

R. WOODRUFF S1GEVENT:

YES

REFERENCE:

10 CFR 50,72# 18530 p_

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DISCUSSION.(CONTINUED)

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OPERATIONAL EVALVATIONS:

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-- SIMULATOR-(7JSCENARIOS),

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7 0F 12 SR0s->AND 2 0F 15 R0s FAILED, T

4 0F 4 CREWS FAILED,

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o-REGION 2 ISSUED A CAL OH MAY 16, 1990, AFTER THE REQUAllFICATION-

FAILURES,

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Jo TREG10N 2 SUPERSEDED:THE CAL ON MAY 21, 1990, BASED ON THE V OPERATIONAL EVALUATION FAILURES, o :.UNiTSil' AND 2 WILL NOT BE RESTARTED WITHOUT APPROVAL BY THE.

REGIONAL ADMINISTRATOR,

,o LOLB INTENDS TO REQUIRE OPERATIONAL EVALUATIONS PRIORiTO RESTART, o

THE LICENSEE WILL RETRAIN AND EXPECTS TO RESTART IN 3 OR m

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90-13 SURRY UNITS 1 AND 2 MAIN TRANSFORMER FAULT

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MAY 22, 1990 PRQELFM THE UNIT 1 MAIN TRANSFORMER FAULTED CAUSING A TURBINE TRIP /

REACTOR TRIP DN UNIT 1 AND A MANUAL REACTOR TRIP FOR UNIT 2.

BOTH UNITS VERE AT 100% POWER, g

CAUSE

UNKNOWN, POSSIBLE INADVERTENT ACTUATION OF FIRE DELUGE SYSTEM IN THE MAIN TRANSFORMER CAUSED A " PHASE A" TO GROUND FAULT TO OCCUR, 1

SAFETY SIGNIFICANCE MINIMAL SAFETY SIGNIFICANCE OTHER THAN CHALLENGES TO SAFETY

SYSTEMS, DJSCUSSION o

MAIN TRANSFORMER FOR UNIT 1 EXPERIENCED A " PHASE A" TO GPOUND FAULT AND SUBSEQUENT EXPLOSION, o

UNIT 1 RECEIVED A TURBINE TRIP / REACTOR TRIP, o

NON-SAFETY-RELATED LOADS FAST TRANSFERRED, EXCEPT RCP "1A" i

TRIPPED, o

RCP "1A" TRIPPED DUE TO LOCK 0UT OF RESERVE STATION TRANSFORMER o

ED 3A 0 STARTED ON UNDERVOLTAGE CONDITION AS A RESULT OF RSS "A" LOCK 0UT, c

UNIT 2 ( AT 100% POWER) WAS MANUALLY TRIPPED BY OPERATORS, o

RSS "A" LOCK 0UT WAS DUE TO ARCING THAT JUMPED FROM THE FAILED MAIN TRANSFORMER TO RSS "A",

CAUSING RSS "A" TO EXPERIENCE VOLTAGE SWINGS, o

EXISTING PLANT LOGIC REQU!RES THE TRIPPING OF ONE OF THE MFW

j PUMPS AFTER A TURB1NE TRIP / REACTOR TRIP TO PREVENT GVERFEEDING i

THE S/Gs, THIS LOGIC WAS TO TRIP THE "C" MFW PUMP OFF OF RSS "B",

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r CON 1ACT:

J, THOMPSON SIGEVENT:

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REFERENCE:

10 CFR 50.72# 18550 AND PNO-II-90-27 lf US

...SURRY; UNITS 11AND'2 2'-

90-13 DISCUSSION (CONTINUED) 4 o

WHEN RSS'"A" WAS LOST, UNIT 1 LOST BOTH MFW PUMPS.

FOLLOWUP o

LICENSEE HAS ROOT CAUSE TEAMS INVESTIGATING TRANSFORMER FAILURES (MAIN XFMR 1 AND PSS "A).

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o EAD WILL FOLLOW TO UNDERSTAND FAILURES AND GENERIC AND SAFETY-IMPLICATIONS, i

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES i-SCRAMS FOR WEEK ENDING 05/20/90 SCHAM CAUSE POWER HUMBER

1990 1989 1988 1987 1986 OF WEEKLY WEEKLY _ WEEKLY WEEKLY WEEKLY:

SCRAMS (5)' AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD '(3)(4)

• • POWER >15%

' EQUIP RELATED >15% 5 3.0 2.9 3.1 3.9' 4.3 PERS. RELATED(6) >15% 1 0.6

1. 0 -

1.0 1.3 '1.8 WHER(7).

>15%

0 0.0 0.1' O.5 1.2-O.4

• • Subtotal **

6 3.6 4.0 4.6 6.4 6.5

** POWER <15%

. EQUIP. RELATED <15% 1 0.4 0.4 0.5 1.2 1.4 PERS. RELATED ' 15% 0 0.1 0.3 0.3 0.6 0.8 MHER <15% 0 0.0 0.7 0.1 0.3 0.2

• • Subtotal **

1 0.5 1.4 0.9 2.1 2.4 7 4.1 5.4 5.5 8,5 8.9 MANUAL VS AlTID SCRAMS TYPE NUMBER 19s0 1989 1988 1987 1986 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD M AL SCRAMS 2 1.0 0.9 1.0 1.4-1.0 AUTOMATIC SCRAMS 4 3.1 3.8 4.5 7.0 7.9 4-

i a s \\ NOTES .1.- PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH 111DNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE. =ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED l l 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 ERRCRS UNRELATED TO CAUSE OF SCRAM. 3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL c DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL + l PROBLEMS. -4, "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES.(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE. L OEAB SCRAM DATA g Manual-and Automatic Scrams for 1986 ------------------ 461 1 Manual and' Automatic Scrams for 1987 ------------------ 439 l Manual and Automatic Scrams for 1988 ------------------ 287 Manual and Automatic Scrams for 1989 ------------------ 244 Manual and Automatic Scrams for 1990 (YTD 05/13/90) --- 75 I .k}}