ML20153H444

Forwards List of Attendees & Events Discussed During 880426 Operating Reactors Events Meeting 88-17.View Graphs Encl

ML20153H444
Person / Time
Site:	Grand Gulf, Waterford, 05000000
Issue date:	04/27/1988
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
NUDOCS 8805130005
Download: ML20153H444 (16)

Text

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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 April 26, 1988 MEETING 88 17 On April 26, 1988 an Operating Reactors Events meeting (88-17) was held to .

i brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on April 19, 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 a report-to-date of long-tern followup assignments and a summary of reactor scrams. No significant events were ,

identified for input to NRC's performance indicator program. No events were ,

suggested for long-term followup.

% 1rM N w tby  ;

tay= 3,taugyg  ;

Wayne Lanning, Chief Events Assessment Branch '

Division of Operational Events Assessment Office of Nuclear Reactor Pegulation

Enclosures:

As stated cc w/Enclo.: ,

See Next Page <

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1. Murley,12G-18 J. Sniezek, 12G-18 F. Miraglia. 12G-18 J. Forsyth, INP0 E. Jordan, AE00 J. Calvo, 130-18 E. Beckjord, NL-007 M. Harper, EWS-263 W. Russell, RI B. Davis, RIII B. Davis, RIII L. Kintner,148-20 J. Nelson Grace, RII E. Adensam,148-20 R. D. Martin, RIV J. Wigginton, 13D-18 J. B. Martin, RV W. Vane, RI L. Reyes, RI!

E. Greenman, RIII J. Callan, RIV D. Kirsch, RV i S. Varga, 14E-4 D. Crutchfield, 13A-2

, B. Boger, 14A-2 G. Lainas, 14H-3 G. Holahan, 13E-4 L. Shao, 8E-2 J. Partlow, 9A-2  ;

B. Grimes, 9A-2 I F. Congel, 10E-4 i E. Weiss, AEOD ,

! S. Black, 12E-4  ;

i T. Martin, 12G-18  ;

1 J. Stone, 90-4 R. Hernan, 13H-3 H. Bailey, AE0D J. Guttmann, SECY A. Thadar.i. 7E-4

. S. Rubin, AEOD '

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\...../ l g :1 W l MEMORANDUM FOR: Charles E. Rossi Director Division of Operational Events Assessment j Office of Nuclear Reactor Regulation l FROM: Wayne Lanning, Chief l Events Assessment Branch i Division of Operational Events Assessment l Office of Nuclear Reactor Pegulation l

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING April 26, 1988 - MEETING 88-17 On April 26, 1988 an Operating Reactors Events meeting (88-17) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on April 19, 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 a report-to-date of long-term followup assignments and a suninary of reactor scrams. No significant events were  ;

identified for input to NRC's performance indicator program. No events were i suggested for long-tem followup, ys g Wa e L nning, Chief Events Assessment Division of Operational Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/Enclo.:

See Next Page

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS RRIEFING (88-17)

April 26,1988 NAME ORGANIZATION NAME ORGANIZATION A. Vietti-Cook- OSP/CP P. Baranowsky NRR/DOEA M.L. Reardon NRR/DOEA R. Lobel NRR/DOEA C. Schulten NRR/DOEA E. Tomlinsen NRR/DRSP T. Greene NRR/DOEA C. Miller OCM/FB W. Minners NRR/DRPS 4

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ENCLOSURE 2 ,

1 OPERATING REACTORS EVENTS BRIFFING 88-17 EVENTS ASSESSMENT BRANCH LOCATION: 12-B-11 WHITE FLINT r TUESDAY april 26, 1988, 11:00 A.M.

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THIS INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 21449.-

1 WATERFORD 3 LOOSE PART FROM MSIV IN STEAM LINE r

WATERFORD 3 CEA INADVERTENTLY WITHDRAWN DURING l' REFUEllNG GRAND GULF 1 LOOSE PARTS INDICATION 4

88-17 WATERFORD 3

LOOSE PART FP0M MSIV IN STEAM LINE APRIL 10 - 11, 1988 i

PROBLEM i

A GATE GillDE CAME LOOSE FROM THE MSIV 0F THE "B" STEAM GENERATOR.

PORTIONS BECAME LODGED IN THE STRAINER FOR THE MAIN TURBINE THROTTLE 1 VALVE, E

FASTENERS HOLDING THE RAIL TO THE SKIRT FAILED - INVESTIGATION ONG0ING.

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SIGNIFICANCE i THE VALVE AFTER FAILURE COULD STILL PERFORM ITS FUNCTION, POTENTIAL j FOR DEGRADED PERFORMANCE, t i

~ DISCllSSION  ;

o MSIVs MADE BY ACF INDUSTRIES, SIMILAR MSIVs USED AT SAN ONOFRE 2/3.

i o GUIDE IS 2 1/2 FEET X 2 INCHES X 3 INCHES.

3 o PARTS OF BROKEN FASTENERS FOUND WITHIN STEAM LINE, o ONE DOWNSTREAM GillDE FOUND IN STRAINER IN TWO PIECES.

o ONE DOWNSTREAM GUIDE FOUND IN VALVE BODY, j o UPSTREAM GUIDES INTACT BUT AB0llT HALF 0F THE FASTENERS HAD FAILED, o POSSIBLE ROOT CAUSES ARE UNDER INVESTIGATION:

J FOLLOWUP

o REGION IV HAS THE LEAD, *

( o EMEB WILL TAKE THE LEAD IN ANY GENERIC ACTION, 1

o EAB CONTACTED REGION V ABOUT SAN ONOFRE 2/3, I

i j CONTACT: E. TOMLINSON 1

REFERENCE:

MORNING REPORT 04/11/88 l

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CEA INADVERTENTLY WITHDRAWN DilRING REFUELING l APRIL 23-24, 1988 PROBLEM l'

l o ON APRIL 23, 1988 (0530) THE LICENSEE NOTICED THAT ONE OF THE FIVE-FINGERED CONTROL ELEMENT ASSEMBLIES (CEA's) WAS STILL LATCHED i

TO THE UPPER GUIDE STRUCTURE ASSEMBLY (UGSA) WHILE LIFTING THE UGSA '

FROM THE VESSEL.

! CAUSE l UNKNOWN SAFETY SIGNIFICANCE WORST CASE SCENARIO IS A DROPPED CEA OVER THE CORE. NO REACTIVITY CONCERN DUE TO HEAVILY BORATED CONDITIONS DURING REFUELING DISCUSSION o USING A SPECIAL TOOL AND CHAIN HOIST, THE LICENSEE MANAGED TO PULL j

THE CEA EXTENSION SHAFT INTO THE UGSA WITH 15 INCHES EXTENDING OUT l THE BOTTOM 0F THE UGSA. I o LICENSEE USED A SUBMARINE-EQUIPPED CAMERA TO VERIFY WHICH CEA WAS l

STILL LATCHED.

l 0 THE LICENSEE MANAGED TO MOVE THE UGSA OVER THE REACTOR VESSEL FLANGE i AND TO THE REFUELING WATER POOL AND DE-LATCHED THE CEA.

O CEA REMAINS AT THE BOTTOM 0F THE P0OL UNTil 0FFLOADING OF FUEL IS COMPLETE. i l

FOLLOWUP o LICENSEE PLANS TO VISUALLY INSPECT CEA FOR DAMAGE AND TO

, SEE IF THEY ARE ABLE TO REUSE THIS CEA.  ;

o THIS HAS HAPPENED AT OTHER PLANTS (CRYSTAL RIVER AND ANO-1).

I CONTACT: J. THOMPSON

REFERENCE:

MORNING REPORT 04/25/88

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- AND LIFT HIG FUEL HANDLING EQUIPMENT ARRANGEMENT (TYPICAL)

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1 88-17 GRAND GULF 1 LOOSE PARTS INDICATION l

APRIL 9, 1988  !

PROBLEM LOOSE PARTS MONITORING SENSOR PICKED UP NOISE IN THE "B" RECIRCULATION LOOP. '

CAUSE SOURCE IS THOUGHT TO BE A VIBRATING PART IN FLOW CONTROL VALVE.

1 SIGNIFICANCE POTENTIAL TO DAMAGE FLOW CONTROL VALVE. ALSO PART CAN DISENGAGE AND I

DAMAGE RECIRCULATION PUfP, JET PUMP, VALVES, FUEL RODS, OR ANY COMPONENT OR EQUIPMENT THE PART COMES IN CONTACT WITH. r DISCUSSION o MAINTENANCE WORK PERFORMED ON FLOW CONTROL VALVE LAST REFUELING t OUTAGE. i

o ON 04/09/88 INCREASED POWER FROM 70% TO 100%.

1 o LOOSE PARTS MONITORING SENSORS PICKED UP NOISE IN "B" RECIRCULATION LOOP.

i o TWO SENSORS: ONE LOCATED 20 FEET DOWNSTREAM 0F FLOW CONTROL VALVE ,

AND ONE LOCATED 20 FEET DOWNSTREAM 0F SUCTION ISOLATION VALVE.

i o ON 04/20/88 NRR WAS INFORMED.

o B&W REPRESENTATIVES ON SITE REFINING ANALYSIS OF NOISE.

j o CONCLUSIONS ARE:

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) (A) NOISE COMING FROM FLOW CONTROL VALVE IN PIPING 0F "B" RECIRCULATION LOOP.

(a) SOUNDS LIKE METAL-TO-METAL CONTACT, j o LICENSEE HAS CHECKED ALL RECIRCULATION PUMP PARAMETERS AND FOUND j THEM NORMAL.

, o LICENSEE HAS VARIED FLOW IN RECTRCULATION PUMP SEAL, RUCU SYSTEM AND CRD. ALSO PERFORMED JET PUMP Sl!RVEILLANCE TESTING. NOISE j REMAINED THE SAME.

CONTACT: T. GREENE i i

REFERENCE:

MORNING REPORT 04/21/88 '

o LICENSEE REDUCED FLOW IN "B" RECIRCULATION LOOP TO 85%, NOISE GREATLY REDUCED.

o LICENSEE HAS REQUESTED GE TO DETERMINE WHAT ADDITIONAL INSTRUMENTS ARE NEEDED TO MONITOR FLOW CONTROL VALVE AND ASSESS POSSIBl.E CAllSES OF NOISE IN FLOW CONTROL VALVE.

E0LLOWUP_

THE REGION AND EAB ARE CONTINlllNG TO FOLLOW EVENT,

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1. PLANT SPECIFIC OATA SASEC CN INITIAL REVIEU OF EC.72 REPORTS FOR THE WEEK OF IllTEREST. PERIOD !! MICNIGHT SLt. DAY THROUGH MIDNIGHT: SUNDAY SCRAMS ARE DEFlilEO AS REACTOR FROTECTIVE ACTUATIONS WHICH RESULT IN R00 MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUT 00WN IN ACCCRDANCE WITH A PLANT PROCECURE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.

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2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR l PERSONNEL ERRORS UhRELATED TO CAUSE OF SCRAM.

3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR. PROCEDURAL DEFICIENCIES. AND MANUAL STEAM GENERATOR LEVEL CONTROL P ROBLEMS.

4 "0THER" IllCLUDES AUTOMATIC SCRANS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN. OR UNKNOWN CAUSE.

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