ML20196J785

Summary of Operating Reactors Events Meeting 88-10 on 880308.List of Attendees & Significant Elements of Events Discussed Encl

ML20196J785
Person / Time
Site:	Davis Besse, Crystal River, Farley, Robinson, 05000000
Issue date:	03/10/1988
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-88-010, OREM-88-10, NUDOCS 8803150053
Download: ML20196J785 (19)

Text

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!!EMORANDUM 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 SLEJECT:

THE OPERATING REACTORS EVENTS MEETlhG March 8, 1988 - MEETING 88-10 OnMarch8,1988anOperatingReactorsEventsmeeting(88-10)washeldto brief senior managers from NRR, RES, AE00 and Regional Offices en events which occurred since our last meeting on March 1, 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, one event suggested for long term followup, and a sunnary of reactor scrams.

Two significant events were identified for input to NRC's performance indicator program.

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Way e anIIing, Chi Events Assessment B Division of Operational Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

As stated l

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T. Murley J. Snterek F. Miraglia J. Forsyth, INPO E. Jordan A. DeAgazio E. Beckjord K. Perkins W. Russell, RI H. Silver B. Davis, RIII H. Perkow J. Nelson Grace RII E. Reeves R. D. Martin, RIV E. Adensam J. B. Martin, RV R. Lo W. Kane, RI L. Reyes, RI!

E. Greenman, RIII J. Callan, RIY D. Kirsch, RV S. Yarga 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. Guttrann A. Thadani S. Pubin I

-i ENCLOSURE 1 LIST OF ATTENDEES OPERATING PEACTORS EVENTS BRIEFING (88-10)

March 8, 1988 NAME ORGANIZATION NAME ORGANIZATION J. Sniezek NRR/DOEA T. Murley NRR W. Lanning NRR/DOEA S. Yarga NRR/DRP C. Schulten NRR/DOEA G. Klingler NRR/PMAS M.L. Reardon NRR/DOEA J. Heltemes AE00 A. Thadani NRR/ DEST C.E. Rossi NRR/00EA G. R. Mazetis PES /DRPS R. Jones NRR/SRXB W. Treskoski OEDO J. Ramsey NRR/DOEA G. Lainas NRR/ADR II J. Roe NRR/DLP0 D.H. Moran OSP/TVA J. Carter NRR/DOEA W. Jensen NRR/DOEA A. DeAgazio NRR/PD 3-3 D. Tondi NRR/ DEST R.W. Woodruff NRR/DOEA P. Rang NRR/SELB H. Berkow NRR/PD 2-2 R. Lo NRR/PD II-1 J. Partlow NRR/DRIS B. Boger NRR/ADRI M. Caruso NRR/DRSP P. Wen NRR/DOEA E.G.Adensam NRR/DRPR i

R. Cilimberg NRR/RVIB T.M. Novak AEOD/DSP l

E. Baker NRR/RVIB B. Hayes O!

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n ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-10 LOCATION:

12-B-11 WHITE FLINT TUESDAY, MARCH 68, 1988, 11:00 A.M.

THIS INFORMATION MAY ALSO BE OBTAINF

'Y DIAllNG EXTENSION 21449, l

DAVIS BESSE 1 P

BLE COMMON MODE VALVES CRYSTAL RIVER 3 FEEDWATER MALFUNCTION TURBINE TRIP FAILED FARLEY 1 & 2 POTENTIAL BINDING OF CHARGING PUMPS ROBINSON 2 SINGLE FAILURE VULNERABILITY /

I EDG TRIPS PREVENTED RESTART

PAVIS BESSE 1 POSSIBLE COMMON MODE VALVE FAILURE MARCH 4, 1988 PROBLEM SERVICE WATER (SW) OUTLET VALVE SE 1834 FOR COMPONENT COOLING WATER (CCW) HEAT EXCHANGER #2 DRIFTED FROM 100% OPFN TO 30% OPEN, SICL.FICANCE POSSIBLE COMMON MODE FAILURE MECHANISM BY WHICH OUTLET VALVES TO BOTH DECAY HEAT REMOVAL (DHR) HEAT EXCHANGERS AND BOTH (CCW) HEAT EXCHANGERS MIGHT BE INOPERABLE SINCE THE VALVES ARE SIMILAR.

DISCUSSION o

PREVIOUS HISTORY OF VALVE FAILURE, o

MARCH 3 ONE VALVE DECLARED OUT-OF-SERVICE, o

AT 18: 43 ON MARCH 4, THE LICENSEE WAS TROUBLESHOOTING VALVE SW 1434, o

VALVE SW 1434 DRIFTED FROM THE REQUIRED FULL OPEN POSITION TC 30%

FULL OPEN.

AIR REQUIRED TO REMAIN OPEN, o

BOTH TRAINS OF DHR WERE lECLARED IN0 PERATIVE SINCE CCW OUTLET VALVES OF DHR HEAT EXCHANGth: AND SW OUTLET VALVES OF CCW HEAT EXCHANGERS ARE THE SAME DESIGN, o

LICENSEE DECLARED ALERT, o

BY 18:55 LICENSEE HAD MANUALLY OPENED AND REMOVED POWER FROM VALVES FOR DHR AND CCW TRAIN # 2 ENDING THE ALERT, o

CONTINUING PROBLEM WITH CCW 8 SERVICE WATER VALVES DUE TO OVER TOROUE AND CORR 0SION, o

MODIFIED EMERGENCY PROCEDURES TO VERIFY VALVE POSITION, o

TWO TRAINS OF CCW AND DHR NOW OPERABLE, o

REFUELING OUTAGE STARTS 1:00 A.M. MARCH 10.

PLANT TO BE DOWN FOR 6 MONTHS, FOLLOWUP o

REGION TO REQUEST 50,59 EVALUATION TO JUSTIFY OPERATION WITH LOCKED OPEN VALVE, o

LICENSEE ?,EDESIGNING SYSTEM, CONTACT:

W. JENSEN

REFERENCE:

50,72 #11668

4 CRYSTAL RIVER 3 FEEDWATER MALFUNCTION TURBINE TRIP FAILED FEBRUARY 28, 1988 PROBLEM A FEEDWATER MALFUNCTION CAUSED REACTOR TRIP, THE TURBINE DID NOT TRIP, SIENJFICANCE B&W DESIGNED REACTORS HAVE A HISTORY OF SENSITIVITY TO FEEDWATER MALFUNCTIONS, DISCUSSION o

ON FEBRUARY 28, 1988 POWER WAS BEING REDUCED FOR MAINTENANCE ON THE MAIN GENERATOR, o

AT 45% POWER THE INTEGRATED CONTROL SYSTEM (ICS) BEGAN INCREASING FEEDWATER FLON TO THE B STEAM GENERATOR (SG),

o CAUSED BY IMPROPER REG VALVE POSITIONING (YOKE NUT FLANGE FACE SEVERED, 2 1/2 INCHES OF PLAY) o THE ICS SENSED THE MISMATCH OF POWER TO FEED FLOW, STOPPED INCREASING FEED FLOW AND CLOSED THE LOW LOAD VALVE, o

THE OPERATOR OPENED THE MAIN FEEDWATER CROSSTIE VALVE TO BALANCE FLOW TO THE 2 SGs, o

THE CROSSTIE VALVE IS INTERLOCKED TO CLOSE THE B-MAIN FEFDWATER REG VALVE, o

ALL FEEDWATER LOST TO B-SG, o

REACTOR TRIP ON WIGH REACTOR SYSTEM PRESSURE, o

THE TURBINE WOULD NOT TRIP AUTOMATICALLY OR MANUALLY FROM THE CONTROL BOARD, o

DEFECTIVE SOLEN 0ID SPRING AND CORRODED FUSE HOLDER PREVENTED TRIP, o

OPERATOR TRIPPED THE MAIN GENERATOR 14 SECONDS AFTER REACTOR TRTP (OPENED GENERATORS BREAKERS) AND CLOSED MSIVs, o

TURBINE TRIPPED FROM THE YARD, o

THE B-SG LEVEL DECREASED TO THE EMERGENCY STEAM GENERATOR SETPOINT AND.TWO AFW PUMPS WERE ACTUATED, o

PREVIOUS TURBINE TRIP FAILURE LAST YEAR FROM DIFFERENT CAUSE (FAILED LOCK 0UT RELAY - LER 8711)

CONTACT: W. JENSEN

REFERENCE:

50,72 #11626

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FOLLOWUP'

-REGION II IS MONITORING. LICENSEE'S REPAIRS 0F THE MAIN FEEDWATER

, REG VALVE - Ai!D TURBINE TRIP' S0LEN0ID, 3

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FARLEY l 8 2 E0TENTIAL BINDING 0F CHARGING PUMPS MARCH 3, 1988 PROBLEM 50 CU FT OF HYDR 0 GEN WAS FOUND IN THE SUCTION HEADER FOR THE CHARGING PUMPS FOR EACH UNIT, CAUSE PIPING CONFIGURATION AND DIFFERENTIAL SOLUBILITY OF HYDROGEN.

SIGNIFICANCE BINDING OF ONE TRAIN OF HPSI PUMPS WHEN THE LPSI PUMPS TRANSFER FROM THE RWST TO THE CONTAINMENT SUMP DURING A LARGE LOCA, DISCUSS!ON o

ON 02/26/88, THE LICENSEE WAS CONCERNED ABOUT THE BORON CONCENTRATION IN UNIT 1 AND PREPARED TO TAKE A COOLANT SAMPLE FROM THE CHARGING PUMP SUCTION HEADER AT THE POINT SHOWN ON THE ATTACHED DIAGRAM, o

A RUN OF PIPING CONNECTED TO ONE END OF THE SUCTION HEADER IS

ELEVATED, o

54 CU FT HYDROGEN WAS VENTED BEFORE COOLANT WAS ORTAINED, o

UNIT 2 WAS VENTED AND 51 CU FT OF HYDROGEN WAS FOUND, o

THE VOLUME CONTROL TANK IS APPARENTLY THE SOURCE OF HYDROGEN, o

SOLUBILITY OF HYDROGEN IS DIRECTLY PROP 0RTIONAL TO PRESSURE, o

6 CU FT OF GAS WILL BIND A CHARGING PUMP, o

TRANSPORT RATE TO THE HEADER IS APPR0X 5 CU FT PER DAY, o

THE LICENSEE IS VENTING EVERY 8 HR AND CONSIDERS THE PUMPS

OPERABLE, FOLLOWilP o

WESTINGHOUSE IS PROVIDING A WRITTEN SAFETY ANALYSIS, o

BECHTEL IS DETERMINING THE REASON FOR THE PIPE ELEVATION, o

EAB IS CONTINU3NG TO FOLLOW THIS EVENT, CONTACT:

R. WOODRL'FF

REFERENCE:

DR 03/07/88

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s ROBINSON 2 SINGLE FAILURE VULNERABILITY /EDG TRIPS PREVENTED RESTART PROBLEMS o

SI PUMPS SUSCEPTABLE TO SINGLE FAILURE, o

POSSIBLE COMMON MODE FAILURE OF EDGs, DISCUSSION o

01/29 - UNIT SHUTDOWN BECAUSE SINGLE FAILURF 0F EMERGENCY ELECTRICAL DISTRIBUTION CAN RENDER 2 0F 3 SI PUMPS INOPERABLE, o

01/30 - 02/10 - IDENTIFIED MANY SINGLE FAILURE SCENARIOS, FIVE SCENARIOS RESOLVED BY MODIFICATIONS, o

02/07 - ADDITIONAL SINGLE FAllllRE OF D.G. VOLTAGE REGULATOR IDENTIFIED, o

02/16 - ONE SI PUMP; LARGE BREAK OK WITH SMALL CHANGE IN F 3 0

SMALL BREAK NEEDS OPERATOR MANUAL SW!TCH0VER OF "B" SI PUMP WITHIN 30 MINUTES OF S,F, OF EMERGENCY ELECTRICAL SYSTEM, o

02/19 - PNSC REJECTED MANUAL SWITCH 0VER OF "B" SI PUMP, o

02/24, O'?/26, 03/01 - TS CHANGE FOR 60% POWER LEVEL, o

03/07 - T.S. CHANGE GRANTED, o

BOTH EDCs (FAIRBANKS-NORRIS) EXPERIENCED 8 OVERSPEED TRIPS DURING PAST 8 l!0NTHS, o

UNDERLY NG CAUSES UNKNOWN, o

INCREASED SURVEILLANCE TESTING TO WEEKLY, CONTACT:

R. L0, P FREDERICKS0N (RII)

REFERENCE:

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H. B. Robinson Emergency Bus Layout For Safety injection Pumps offelte offsite power power Bus E1 Bus E2 7-l I

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EDO - Emergency Diesel Generator SIP -Safety injection Pump

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03/07/89 PERFORMANCE INDICATCRS SISNIFICANT EVEliS FLAN 7 NAPE EVENT EVENT DESCRIP110%

GTR SIGNIFICANCE DATE SPJ G *Or 2 01/02/iB 'RIMArY CtifAINMENT ISCLAllh VA.VIS th TN DFA N O POTENTIAL FCR OR A:Ti.'A'. !ESRADATION TFAh5:E8 LINI! FAILEt TO CL0i!

0F CONTAINMEhi CR SAFETY-RELAi!D STRUtili815 Ih*!W FCMT I

/0 l!' STEAM S!hE".ATCR r.LENEI TO CRY OUT IN V!CtATION CF 0 ADP.!N!!iRATIVE, PROCEIU:aL 41

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SUMMARY

WEEK ENDINE 03/06I68

1. PLMT SPECIFIC DATA

- DATE SITE UN!iP0utRS!6NALCAUSE C0FLI-YTD YTD Yil CATION! ABOVE BELM TdTAL 151 15I 03/02!B8 KEWAUNEE 1

93 A EEUlFMENT

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PLANT SPECIFIC DATA SASEC Ch INITIAL REVIEW 0F EC.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 SHUTDOWN IN ACCORDANCE WITH A PLANT PROCECURE.

THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.

2.

COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UhRELATED TO CAUSE OF SCRAN.

3.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL

PROBLEMS, 4.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIR0l! MENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UllKNOWN CAUSE.

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3 Id i 0 W MEMORANDUM 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 March 8,1988 - MEETING 8810 On March 8,1988 an Operating Reactors Events meeting (88-10) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last neeting on March 1,1988. 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, one event suggested for long tern followup, and a sunnary of reactor scrams. Two significant events were identified for input to NRC's performance indicator program.

Wayne Lanning, Chief Events Assessment Brar.ch Division of Operational Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/Enclo.:

See Next Page DISTRIBUTION Central File EAB Reading File Circulating Copy EAB Staff MLReardon, EAB 00udinot, EAB LKilgore, SECY, PDP OFC :EAB:NPR

C:EAB:NRR

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DATE n3/Oy88

/A /pF88 OFFICIAL REC D COPY