ML20044A209

Summary of Operating Reactors Events Meeting 90-14 on 900530.On 900524,site Emergency Declared at DC Cook Unit 1 Due to Switchyard Fire.On 900528,feedwater Line Rupture Occurred at Foreign Reactor Due to erosion-corrosion

ML20044A209
Person / Time
Site:	Cook, San Onofre
Issue date:	06/19/1990
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-90-014, OREM-90-14, NUDOCS 9006280208
Download: ML20044A209 (19)

Text

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7 June 19,1990 MEMORANDUM FOR:

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

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

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING May 30, 1990 MEETING 90 14 On May 30, 1990, we conducted an Operating Reactors Events meeting (90 14) to inform senior managers from NRR, ACRS, RES, Commission staff, and regional offices of selected events that occurred since our last briefing on May 23, 1990. lists the attendees. presents the significant elements of the discussed events.

' contains reactor scram statistics for the week ending 05/27/90. tabulates two significant events which have been identified for input into the NRC performance indicator program.

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

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION

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ENCLOSURE 1 LIST-OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (90-It.)

May 30, 1990 NAME ORGANIZATION NAME ORGANIZATION V. Benaroya GPA/IP B. Grimes hRR/DRIS P. Boehnert-ACRS M. Reardon NRR/DOEA A. Mattson NRR/DOEA D. Fischer NRR/DOEA J. Richardson NRR/DET J. Scarborough OCM/KR C. Thomas NRR/DLPQ W. Troskoski OE G. Thomas NRR/ DST A. Young NRR/DOEA J. Ramsey NRR/DOEA N. Campbell NRR/DOEA

f. Witt NRR/EMCB C. Cheng NRR/EMCM S. Koscielny NRR/EMCB F. Miraglia NRR/DONRR P. Cortland NRR/TVA J. Flack RES/SAIB R. Paltemas NRR/DREP K. Wickman NRR/DET R. Koltay NRR/DRIS J. Wechselberger NRR/AD-3 R. Hermann NRR/DET L. Norrholm OCM/KC J. 2wolinski NRR/DRSP W. Jensen NRR/DOEA l

G. Holahan NRR/DRSP J. Larkins NRR/PD-5 i

J. Gua NRR/ DST L. Kokajko NRR/DRSB

0. Chopra NRR/SELB W. Russell NRR/ADT P. Baranowsky NRR/DOEA j

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i ENCLO$URE 2 OPERATil1G REACTORS EVENTS BRIEFING 90-14 EVENTS ASSESSMEllT BRANCH LDCATION:

10B-11, WHITE FLINT WEDNESDAY, MAY 30, 1990, 11:00 A.M.

COOK UNIT 1 DECLARATION OF SITE ALERT DUE TO SWITCHYARD FIRE SAtl Ol10FRE UNIT 3 FEEDRING DEGRADATION FOREIGN REACTOR FEEDWATER LINE RUPTURE

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., i 90-14 COOK UNIT I DECLARATION OF SITE ALERT DUE TO SWITCHYARD Fille MAY 24, 1990 PROBLEM A FIRE'RESULTING FROM THE DESTRUCTIVE FAILURE OF THE CdRRENT TRANSFORMER ASSOCIATED WITH ONE OF THE THREE SINGLE PHASE "L" CIRCUIT BREAKERS.

CAUSE THE CAUSE 0F THE TRANSFORMER FAILURE IS UNDER INVESTIGATION, SAFETY SIGNIFICANCE POTENTIAL THREAT TO OPERABILITY OF SAFETY RELATED EQUlPMENT, DISCUSSION o

AN UNUSUAL EVENT (UE) WAS DECLARED AT 3:10 AM AFTER AN EXPLOS10N AND FIRE OCCURRED IN THE 345 KV SWITCHYARD, o

THE CAUSE OF THE EXPLOSION IS UNDER INVESTIGATION.

THE EXPL0SION OCCURRED IN Tile CENTRAL PHASE CURRENT TRANSFORMER ASSOCIATED WITH THE "L" CROSSTIE CIRCUlT BREAKER IN THE UNIT 1 345 KV SWITCHYARD (SEE ATTACHED DIAGRAM),

o BREAKERS N2, M2, AND K2 OPENED AUTOMATICALLY T0 ISOLATE BUS 2'IN THE 345 KV SWITCHYARD AND BREAKERS A2 AND B2 OPENED T0 ISOLATE BUS 2 IN THE 7G5 KV SWITCHYARD, BREAKER "L1" 0PENED MOMENTARILY, BUT RECLOSED AS DESIGNED.

o THE SITE FIRE BRIGADE AND LOCAL FIRE DEPARTMENTS RESPONDED TO THE SCENE BUT FIREFIGHTING WAS NOT IMMEDIATELY ATTEMPTED.

THE FIRE WAS EXTINGUISHED AFTER EQUIPMENT IN PROXIMITY TO l

THE "L" BREAKER WAS.DEENERGlZED i

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ABOUT THREE HOURS INTO THE EVENT, THE VE DECLARATION WAS l

UPGRADED TO A SITE ALERT WHEN A CUPRENT TRANSFORMER ASSOCIATED L

'WITH THE "K1" CIRCulT BREAKER WAS FOUND TO HAVE SUSTAINED MINOR DAMAGE, l

CONTACT:

N. FIELDS SIGEVENT:

NO

REFERENCES:

10 CFR 50,72# 18562 (UPDATE), MORNING REPORT 05/25/90, PN-Ill-90-33, AND PN-ill-90-33A

L,',:

C00K UNIT 1 90-14 DISCUSSION (CONTINUED) o BOTH UNITS REMAINED AT POWER THROUGHOUT EVENT, ALTHOUGH UNIT 1 OUTPUT WAS REDUCED FROM 70 TO 62 PERCENT TO AfD SWITCHYARD STABILITY, o

THE ALERT DECLARATION WAS TERMINATED AT 11:38 AM AFTER THE 345KV SWITCHYARD WAS RETUPNED TO A STABLE CONDITION, BUS 2 WAS RETURNED TO SERVICE WHEN BREAKERS "M2" AND "K2" WERE CLOSED, BREAKER "Kl" WAS OPENED TO FACILITATE ITS REPAIR (ABOUT 24 HOURS),

o 0FFSITE POWER WAS NEVER LOST DURING THE EVENT, f_0LLOWilP o

REGION 111 DISPATCHED AN ELECTRICAL SPECIAllST AND AN EMERGENCY PLANNING SPECIAllST TO THE SITE, o

REGION FOLLOWUP WILL FOCUS ON POTENTIAL GENERIC IMPLICATIONS AND ROOT CAUSE OF THE FAILURE OF THE " DELLE AHLSTROM" CIRCUIT

BREAKER, I

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90-14 SAN ONOFRE UhdT 3 FEEDRING DEGRADATION MAY 23, 1990 PROBLEM DEGRADATION OF STEAM GENERATOR (SG) FEEDWATER RING JOINT AND FEEDWATER JUNCTION BOX VENT, CAUSE FEEDRING DEGRADATION IS PROBABLY DUE TO THERMAL CYCLIC FATIGUE (DUE TO BATCH FEEDING) AND EROSION, VENT DEGRADATION IS ATTRIBUTED TO HIGH-VELOCITY EROSION, SAFETY SICNIFICANCE SIGNIFICANT DEGRADATION OF THE FEEDRING COULD RESULT IN LOOSE PARTS WHICH COULD DAMAGE SG TUBES - POTENTIAL SG TUBE RUPTURE AND/0R MULTIPLE SGTR's BACK6P00ND o

IN 1982, SONGS 2 & 3 MODIFIED THElR SG FEEDRING SPARGER DUE TO CONCERN FOR WATER HAMMER IN THE J-TUBES FOLLOWING AN AUXILIARY FEEDWATER INJECTION.

o 1982 MODIFICATIONS INCLUDED THE FOLLOWING:

LARGER DIAMETER J-TUBES THICKER FEEDRINGS (SCHEDULE 120 REPLACED SCHEDULE 40 PIPINC)

INSTALLATION OF FEEDRING JUNCTION B0X VENT (SCHEDULE 80),

DISCUSSION o

DURING THE CURRENT REFUELING OUTAGE, LICENSEE FOUND METAL DEBRIS ON THE BOTTOM 0F THE SG, o

VISUAL INSPECTION REVEALED SIGNIFICANT DEGRADATION / EROSION IN THE SCHEDULE 40 PORTION OF THE FEEDRlh0 AND IN THE WELD TO THE JUNCTION B0X ON BOTH SG's, A CRACK WAS FOUND IN THE SCHEDULE 40 STUB WHERE EROSION APPEARS TO HAVE OCCURRED, LICENSEE ALSO FOUND THAT.THE END (0R "T") 0F THE FEEDRING JUNCTION BOX VENT HAD BEEN DISLODGED ON BOTH SG's, CONTACT:

A. YOUNG SIGEVENT:

YES

REFERENCE:

MORNING REPORTS 05/23/90 AND 05/29/90

. SAN ONOFRE UNIT 3 90-14 plSCUSS10N (CONTINUED) o 5 PIECES OF METAL WERE FOUND AND RECOVERED IN SG "88" AND 2 IN SG "89",

THESE PIECES APPEAR TO MAKE-UP THE MISSING PARTS OF THE FEEDRING AND VENT, ALTHOUGH ALL THE MISSING PIECES HAVE BEEN i

ACCOUNTED FOR, 3 PIECES IN SG "89" HAVE NOT YET BEEN REC 0VERED DUE TO UNAVAILABLE TOOLS AND HIGH RADIATION, THE LICENSEE IS STILL MAKING AN EFFORT TO REC 0VER THE MISSING PIECES, o

EXAMINATIONS OF THE SCHEDULE 120 FEEDRING REVEALED NO THINNING r

OR EROSION.

o EDDY CURRENT TESTING OF THE SG TUBES ORIGINALLY REVEALED NO UNUSUAL WEAR OF THE TUBES FOR THE CYCLE.

HOWEVER, ONE TUBE WAS FOUND LAST WEEKEND TO HAVE 30% WEAR / FRETTING ATTRIBUTABLE TO l

DEBRIS, LICENSEE LOWERED THE SETPOINT FOR THE AIR EJECTOR MONITOR ALARN, i

FOLLOWUP o

NRR/EMCB IS CURRENTLY ONSITE OBSERVING METALLURIGICAL EXAMINATIONS OF THE AFFECTED PlPING, o

LICENSEE IS PLANNING TO REPLACE SCHEDULE 40 J01NT WITH SCHEDULE 120 AFTER ROOT CAUSE HAS BEEN DETERMINED, o

NPR AND REGION ARE FOLLOWING LICENSEE'S ACTIVITIES AND ARE EVALUATING FOR GENERIC APPLICABILITY,

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90-14 FOREIGN REACTOR-FEEDWATER LINE RUPTURE MAY 28, 1990 PROBLEM MAIN FEEDWATER PIPE BREAK WITHIN THE TURBINE BUILDING, i

CAUSE DECREASE IN PIPE WALL THICKNESS FROM EROS 10ti-CORROS10N.

RUPTURE TRIGGERED BY CHANGE IN FEEDWATER PUMP OPERATION, F

SAFETY SIGNIFICANCE HAZARD TO PERSONNEL AND VITAL EQUIPMENT, DEGRADATION OF HEAT REMOVAL CAPADILITY FROM THE REACTOR, DISCUSSION o

WITH THE PLANT AT POWER ELECTRICAL MAINTENANCE WAS IN PROGRESS, o

ONE MAIN FEEDWATER PUMP WAS INADVERTENTLY TRIPPED OFF, o

APPARENTLY THE SUDDEN CLOSING OF A CHECK VALVE CAUSED THE 325 MM (12,8 IN) FEEDWATER PUMP DISCHARGE PIPE TO RUPTllRE, o

FEEDWATER PRESSURE WAS 70 BARS (1015 PSI),

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SIGNIFICANT DAMAGE IN THE TURBINE BulLDING TO NEARBY CABLES t

AND PIPING.

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NO SIGNIFICANT DAMAGE TO SAFETY EQUIPMENT, o

OPERATORS MANUALLY TRIPPED THE REACTOR, o

ALL OPERATING MAIN FEEDWATER PUMPS AUTOMATICALLY TRIPPED ON LOW PRESSURE, l

0 BOTH AUX 1LIARY FEEDWATER PUMPS STARTED AS DESIGNED, L

o LITTLE CHANGE IN STEAM GENERATOR LEVEL, o

BEFORE RUPTURE THE BROKEN FEEDWATER PIPE HAD THINNED FROM A WALL THICKNESS OF 18 MM (0,71 IN) TO ABOUT 1 MM, l

o THE BREAK WAS DIRECTLY DOWNSTREAM FROM A FLOW MEASURING

ORIFICE, l.

o THE OPERATING UNIT AT THE TWO UNIT SITE WAS SHUTDOWN FOR I

.lNSPECTION OF-THE FEEDWATER PlPING, SOME THINNING FOUND, RADIATION RELEASE FROM THE EVENT WAS NOT SIGNIFICANT, o

CONTACT:

W, JENSEN

I l't MREIGN REACTOR 90-14 C

L FOLLOWUP 5

o EAB WILL WORK WITH NRR TECHNICAL BRANCHES TO INVESTIGATE-IMPLICATIONS FOR DOMESTIC REACTORS, 1

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

PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.

SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWil IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERAT!llG LICENSE.

2.

COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAU5E 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 DESIGil, OR UNKNOWN CAUSE.

F OEAB SCRAM. DATA Manual and Automatic Scrams for 1986 ------------------ 461 Hanual and Automatic Scrams for 1987 ------------------ 439 Manual and Automatic Scrams for 1988 ------------------ 287 Manual and Automatic Scrams for 1989 ------------------ 244 ManualandAutomaticScramsfor1990(YTD05/27/90)--- 80 i

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PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF S0.72 REPORTS

_FOR THE WEEK OF-INTEREST. PERIOD 15 MIDNIGHT SUNDAY THROUGH HIDNIGHT-SUNDAY.

SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS-OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATillG LICENSE.

2.

COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR

-PERS0!lllEL ERRORS UNRELATED TO CAUSE OF SCRAM.

3 PERSONNEL REl.ATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MAllVAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

4.

"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGil,ORUNKNOWNCAUSE.

OEAB SCRAM DATA tianual and Automatic Scrams for 1986 ------------------ 461 Hanual and Automatic Scrams for 1987 ------------------ 439 Manual and Automatic Scrams for 1988 ------------------ 287 Manual?and. Automatic Scrams for 1989 ------------------ 244 Marual and Automatic Scrams for 1990 (YTD 05/27/90) --- 80 i

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