ML20141N683

Summary of Operating Reactors Events Meeting 86-05 on 860224.Lists of Attendees,Events & Significant Elements Discussed & Assignment of Followup Review Responsibility Encl

ML20141N683
Person / Time
Site:	Fermi, Pilgrim, Turkey Point, Vermont Yankee, Zion, 05000000
Issue date:	03/07/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8603170514
Download: ML20141N683 (18)

Text

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Harold'R. Denton, Director-

. ,, MEMORANDUM FOR: .

Office of Nuclear Reactor Regulation' V: Mj ,

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6 ',,'jFROM:- .-Gary M.- Holahan,; Director ~ ' ' l

'f;, E0perating Reactors Assessment Staff ,

SU8 JECT: ,

.SUpstARY OF.THE~ OPERATING REACTORS EVENTS ~

MEETING ON February 24, 1986 , MEETING 86-05~- ,

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j f- On February 24, 1986, an Operating' Reactor Events meeting-(86-05) was held to:

pA ,;brief the Office Director 'the Division tirectors and their represent. ives on . ,

events which occurred:since our last meeting on February 10,,1986. The sist of ai j%g ,7 attendees;is included as Enclosure 1.

1 a.L The events discussed and the significant elements of these events are presented '

Lin Enclosure 2., In addition, the assignment of follow-up review responsibility.

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was' discussed. .The assignments made during this meeting and the status of-

.previour; assignments are presented in Enclosure 3..

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• Completion dates have been assigned for items in Enclosure 3. 'Each assignee

'should review Enclosure 3 with regard to their respective responsibilities. ~

2.}f ' Note that several-assignments are approaching the due date. Please be responsive aPo and advise 0RA8 (D. Tarnoff, x29526) if the target completion date .cannot

' be met.' '

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?' Gary M. Holahan, Director ,,

P Operating Reactors Assessment Staff.

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Enclosures:

• " As stated

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f ~DISTRI8'UTION i.

Central, Files s') .. ,'7NRC POR 4 n ORA 8 Rdg.

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. 10RA8 Members

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7 1986 -

~ Harold R.~Denton f -2. /

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9 4 D. Lynch-f; cc: D. Eisenhut J. Taylor E. Adensam r

C.'Heltemes- 1 J. Norris S. Varga T. Murley, Reg. I' .

J. Nelson Grace.' Reg. II P. Leech .

J. Keppler, Reg. III J. Zwolinski D.. Martin, Reg. IV D. Mcdonald

.( R.

J. B. Martin, Reg.-V

~

!.. L. Rubenstein R. Starostecki, Reg. I 'il V. Rooney

' R. Walker, Reg. II D. Muller -i1 C. Norelius, Reg. III E. Johnson. Reg. IV >

D. Kirsch, Reg. V H. Thompson F. Miraglia jf a (

R. Bernero T. Spets W. Russell '

T. Novak '

F. Schroeder W.' Houston

8. Sheron D. Ziemann #'

J., Knight ,

D. Crutchfield G. Lainas V. Benaroya W. Regan

. D. Vassallo E. Jordan E. Rossi "e R. Baer-E. Weiss R. Hernan S. Showe S. Rubin f i .

+ - _ _ _ . _ _ _ . _ _ - - _ _ . - - - - _ - _ _ _ - _ - - _ - - _ - _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - . _ _ _ _ _ _ _ . _ - - - - - _ - _ _ _ _ _ _ - _ - _ _ _ .

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ENCLOSURE 1 LIST OF ATTENDEES

-OPERATING REACTORS EVENTS BRIEFING (86-05)-

FEBRUARY 24, 1986 NAME- DIVISION- NAME DIVISION

'R. Hernan NRR/PPAS

.D. L. Ziemann NRR/DHFS. .

D.:Crutchfield NRR/PWR-B- A.- Rubin NRR/DSR0 R. Singh I'

. 'W. Haass IE/VPB IE/EAB E.,Doolittle ' NRR/PWR-A V. Benaroya. NRR/F0B-A ,

D. Vassallo  !

W. Regan- NRR/ FOB-B NRR/ FOB S. Salah AE00/ROA3' E. Adensam- NRR/DSL LL. Hiller NRR/PWR-B D. Allison IE/EAB-M. Caruso . NRR/0 RAS S. Newberry NRR/0 RAS M.'Clausen OCM S. Rubin AE00 A. Dromerick IE/EGCB K. Seyf ri t . AEOD P. Leech NRR/BWD#1 M. Chiramal AE00 D. Mcdonald NRR/PWR-A E. Weiss IE/DEPER J. T. Beard NRR/0 RAS M. J. Virgilio NRR/0 RAS

.G. Holahan NRR/0 RAS B.'Sheron NRR/DSR0 F. Miraglia NRR/PWR-B F. Schroeder NRR/PWR-B G. Lainas NRR/ DBL. R. Baer IE/DEPER D. Lynch NRR/BWD#3 J. Norris NRR/PWR-A 8

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ENCLOSURE.2' p' ._

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- OPERATING REACTORS EVENTS BRIEFING 86-05 .

> FEBRUARY 24,'1986' s

FERMI UNIT'2 EMERGENCY' DIESEL GENERATOR BEARING FAILURES ZION ~ UNIT 2 TWO IN0PERABLE EMERGE":Y DIESEL GENERATORS <

. PILGRIM- RHR HIGH PRESSURE ALARMS LTURKEY P'0lNT UNIT 3 REACTOR TRIP DUE TO PERSONNEL ERROR s.

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. VERMONT YANKEE FAILURE OF STANDBY LIQUID CONTROL-SYSTEM (UPDATE) h

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FERMI UNIT 2 - EMERGENCY DIESEL GENERATOR BEARING FAILURES FEBRUARY 24, 1986, (D LYNCH, NRR)

PROBLEM: CONTINUING FAILURES OF EDG MAIN BEARINGS SIGNIFICANCE: UNRELIABLE ONSITE AC POWER SOURCES  :.

' CIRCUMSTANCES:

'*~ BEARING FAILURE ON EDG'S 11 a 12 (01/85) '

o BEARING FAILURE ON EDG 13 (11/85)

" DISTRESSED" BEARINGS ON EDG'S 11 a 12 (11/85)

'FURTHER EVIDENCE OF " DISTRESSED" BEARINGS (12/85) t

, FOLLOW-UP:-

' LICENSEE, Rill AND NRR REVIEW AND EVALUATION IS CONTINUING' MEETING AT SITE (01/?4/86) '

LICENSEE PROPOSED "GET WELL" PROGRAM ON 02/05/86 TELECON (DEC0, RIII AND NRR) ON 02/14/86 TELECON (ALL 3) ON 02/21/86; DECO PROPOSED ON 02/21/86 VISUAL INSPECTION OF LIMITED NUMBER OF UPPER CRANKLINE MAIN BEARINGS LICENSEE IS COMPLETING DEMONSTRATION RUNS ON EDG'S 11 a'13

• : POST-DEMO INSPECTIONS ON EDG'S.11 a 13 T9 BE STARTED IN WEEK OF 02/24/86 '

NRs EVALUATION TO BE COMPLETED IN EARLY MARCH WITH NRR PROVIDING TECHNICAL ASSISTANCE TO REGION III

- RIII TO ISSUE AGENCY EVALUATION AND POSITIONS ABOUT MID-MARCH COMMISSION BRIEFING IN MID-MARCH FACILITY IS SHUTDOWN; RESTART DATE UNCERTAIN

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ZION 2 - TWO INOPERABLE EMERGENCY DIESEL GENERATORS (EDGs)

FEBRUARY 19, 1986 (J. NORRIS, NRR)

PROBLEM TWO INOPERABLE EDGs AT ZION 2 SAFETY SIGNIFICANCE DEGRADED ON-SITE POWER SOURCES. PLANT UNDER SPECIAL (HPZ) ORDER ON EDGs CIRCUMSTANCES

• AT 22:32 0N FEBRUARY 19, 2A EDG FAILED PERFORMANCE TEST WHEN IT TRIPPED AFTER COMING TO SPEED.

PER TS, ALL REMAINING EDGs INCLUDING SWING EDG WERE TESTED, SWING EDG TRIPPED DUE TO DEFECTIVE RELAY, PER TS, WITH TWO EDGs INOPERABLE UNIT 2 STARTED SHUTTING DOWN.

• ON 2A EDG THE LICENSEE FOUND FUEL LINE VALVE 3/4 CLOSED, AFTER OPENING THE VALVE EDG WAS SUCCESSFULLY TESTED,

• AT 01:35 ON FEBRUARY 20, 2A EDG WAS DECLARED OPERABLE.

THAT PLACED UNIT 2 ON A 7 DAY LC0 WHICH EXPIRES ON FEBRUARY 26, 1986.

FOLLOWUP DURING DIAGNOSTIC TESTING, SWING EDG FAILED AGAIN,

• OVER THE WEEKEND, ZION FOUND FAULTY RELAY ON THE SWING EDG AND REPLACED IT. AFTER PERFORMING 60 SUCCESSFUL ELECTRONICALLY SIMULATED STARTS, THE LICENSEE TESTED THE SWING EDG AND DECLARED IT OPERABLE, THE TWO FAILURES ON THE SWING EDG WERE DECLARED NOT VALID FAILURES BECAUSE THE FAILED RELAY IS BYPASSED ON SAFETY SIGNAL, THE CORRECTIVE ACTION FOR THE 2A EDG FAILURE HAS NOT YET BEEN DETERMINED,

• BOTH ZION UNITS ARE NOW RUNNING AT 100% POWER,

' PILGRIM-RHR HIGH PRESSURE ALARMS

. FEBRUARY 12, 1986'(PAUL LEECH,'NRR)

' PROBLEM: .HIGH PRESSURE IN RHR PIPING, r-SIGNIFICANCE: POTENTIAL OVERPRESSURE RESULTING IN AN INTERSYSTEM LOCA',:

CIRCUMSTANCES:

PLANT WAS OPERATING AT f 'LL POWER,

.RHR PIPING WAS BEING PRESSURIZED AB0VE NORMAt BY BACK LEAKAGE 0F PRIMARY COOLANT THROUGH A CHECK LVALVE AND A MOTOR-0PERATED INJECTION VALVE IN LPCI LOOP "B",

ANNUNCIATOR ALARMS OF HIGH PRESSURE (> 400 PSIG) IN c RHR PIPING OCCURRED PERIODICALLY FOR SEVERAL WEEKS UNTIL THE.'M,0, VALVE (1001-28B) WAS MANUALLY TIGHTENED ON FEBRUARY.12.

LICENSEE. ESTIMATED LEAKAGE THROUGH THE M,0, VALVE AT LESS THAN 0,001 GPM,

.TOROVE SWITCH ON THE VALVE (1001-28B) WAS FCUND SET T00 LOW FOR COMPLETE CLOSURE, IT WAS REPLACED AND RESET, BACK LEAKAGE THROUGH CHECK VALVE IS UNKNOWN, NO.'FURTHER ALARMS HAVE OCCURRED, FOLLOW-UP LICENSEE IS REVIEWING THE EVENT TO DETERMINE WHETHER ADDITIONAL ACTION IS NECESSARY, RESIDENT INSPECTOR WILL REPORT ANY RESUMPTION OF THE ALARMS AND RESULTING ACTIONS, NRR WAS INFORMED THAT THE CHECK VALVE IS A HORIZONTAL TILTING DISC TYPE W'llCH IS NOT TESTABLE DURING OPERATION, PREVENTIVE MAINTENANCE WAS PERFORMED DURING ,

LAST REFUELING OUTAGE, LEAK RATE TESTING OF THE CHECK VALVE IS NOT REQUIRED BY TECHNICAL SPECIFICATIONS, THIS TYPE OF EVENT IS BEING CONSIDERED AS PART OF A 3ENERIC ISSUE 105, " INTERFACING SYSTEM LOCA AT BWRS."

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i 1 TURKEY POINT UNIT 3 - REACTOR TRIP DUE TO PERSONNEL ERROR f FEBRUARY 11, 1986 (D. MCDONALD, NRR)_

PROBLEM:

INADVERTENT OPENING 0F DC CIRCUIT BREAKER. - FOLLOWUP ACTION RESULTS IN REACTOR TRIP (OPERATOR ERROR) i SAFETY SIGNIFICANCE:

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INAPPROPRIATE OPERATOR ACTION RESULTING IN PLANT TRANSIENT CIRCUMSTANCES:

UNIT 3 100% POWER AND UNIT 4 IN REFUELING - DUE TO PROTECTIVE '

COVER MISSING DURING CONSTRUCTION WORK, CIRCUIT BREAKER INADVERTENTLY OPENED TRIPPING THE CHANNEL 1 HIGH CONTAINMENT PRESSURE LOGIC.

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0FF-NORMAL OPERATING PROCEDURES'USED - ANNUNCIATOR LIST 8 125VDC GROUND LOCATION (INAPPROPRIATE PROCEDURE)

SECOND DC CIRCUIT BREAKER CYCLED MANUALLY (PER PROCEDURE)

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(CHAN 3 HI CONT. PRESS.)

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- 2/3 LOGIC WAS SATISFIED, YIELDING ESF ACTUATION, CONTAINMENT ISOLATION TRAIN A, AND REACTOR SCRAM.

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TRAIN B LOGIC DISABLED BY OPENING OF INITIAL DC CIRCUIT BREAKER FOLLOWUP: ,

VERIFIED SEQUENCE OF EVENTS l

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TESTING B TRAIN PRIOR TO STARTUP ,

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ROOT CAUSE AND CORRECTIVE ACTIONS t

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, -VERMONT YANKEE - FAILURE OF STANDBY LIQUID' CONTROL SYSTEM-

- FEBRUARY-8, 1986' UPDATE - (ERIC WEISS,IE) 1 PROBLEMS SLCS SQUIBLVALVE FAILED'TO FIRE DURING ANNUAL TEST, CONDUCTED c 10N FEBRUARY.8,'1986 i ~* PLANT, WIRING IN TERMINAL BOX INCORRECT ,

' SQUIB-VALVES'HAD INCORRECT PIN-TO-BRIDGEWIRE GROUPING .

. CONTROL R0OM INDICATION OF " CIRCUIT.' CONTINUITY" WAS FALSE

.I SIGNIFICANCE 0THER PLANTS COULD HAVE DEFECTIVE SQUIB VALVES i'

• IF: PROBLEM OCCURS-IN FUTURE, FALSE INDICATION IS MISLEADING CIRCUMSTANCES a' -

MANUFACTURING MOVED FROM NEW YORK TO FLORIDA'IN 1983 TRAVELER" MA'Y HAVE CAUSED CONFUSION CONAX ENGINEER AT VERMONT YANKEE ON FEB-19, 1986 CONFIRMED '

. ASSEMBLIES WERE DEFECTIVE '

y P0TENTIALLY AFFECTED LICENSEES NOTIFIED BY REGIONS-

-SOME SUSPECT SQUIBS DISTRIBUTED OVERSEAS x- *-

NO OTHER DEFECTIVE ASSEMBLIES IDENTIFIED

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' s?F0LL'0WUP O '*' IE NOTICE ISSUED FEBRUARY 21, 1986

/ IE NOTICE'TO BE SENT TO INTERNATIONAL PROGRAMS.

IE' VENDOR INSPECTION PLANNED i

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POTENTIALLY SUSPECT S0VIB VALVE ASSEMBLIES PRIMER PART NUMBER ASSEMBLY PLANT OF PIECES SERIAL NUMBERS

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1617-139-01 VERMONT YANKEE 6 (DEFECTIVE) 552-557 1617-139-01 DRESDEN 6 546-551 1621-240-01 SHOREHAM 7 635-640, 668 1621-240-01 DUANE ARNOLD 6 669-674 1621-240-01 SUSQUEHANNA 19 675-681, 686-697 1621-240-01 LIMERICK 10 699-708 1621-240-01 PILGRIM 3 659-661 NRC REGIONAL REPRESENTATIVES HAVE CONTACTED THE ABOVE FACILITIES BY TELEPHONE.

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ATTACHMENT 1 - SQUlB SCHEMATIC

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SUMMARY

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1. PLANT S*ECIFIC DATA pp E -' ' UNIT POWER REE C#' CO"tPL I a vTD CATIONE T*

02/10/G6 MILLSTONE  : 1 fr A FEREOP'NEL - ' ND 0 02/iO/66 LIMERIC6: 1 100 A EQUIF/FHC PEG NO 3 CC/10/86 EEAVER VALLEY 1 100 A EQUIP /VITf4L EUS NO. 1 02/11'/86' TURKEY POINT 2 100 A PERSONNEL NO i 02/11/86 ARKANSAS 2 100 A EOUIP NO 1 02/13/S6 EEAVER VALLEY 1 OA PERSONNEL NO 2 35 A PERSONNEL NO 7 >

. 02/12/06 RIVER.EEND. 1 4

O2/12/66' MILLSTONE 3 25 A PERSONN'.iL /OPER NO 11 A EOUIP> NO 2 a 02/12/86 GRAND GULF 1 ,

02/13/86 MILLSTONE 2 '14 A EQUIP NO -

- 5 l 02/16/06. LASALLE 2 98 A EQUIP / BOP NO 1

- 02/16/86'SURRY 2 16 A EQUIP /FD VLV NO -1 R v4p e

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. II. CO*1tARISON OF WEEl:LN STA.TIETICE WITH INDUEThY AVE 5 *'-5 E!

t SCRAMS FOR WEEK ENDING

}- 02/ l e>/ 86 f SCRAM CAUSE POWEF: NUMBER NUMBER lo?S OF NOF'MALIZED(6) 'v 7 D L SCR AMC (3 ) TO 1985 AVEt?st

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• • POWER S 15*/.

• 5 5.O 5.4 f .i S *.

ECUIP. RELATED >15%

PERS. RELATED(7) >15% .. . O 2.O (2?*a OTHER(E) >15% 0 0.O O.6 ' 7%*

-** Subtotal $4 8 8.O 8. 9

• t POWER.<15%

EDUIP. RELATED <15% 2. 2.0 1*. 2 ( 5 4 *.

' O.9 (~ED PERS. RELATED <15% 'O OTHER <15% 0 O.0 0.2 ( 6' i

• • Suttotel **

4 4.O 2.4

• • • Total ***

12 12.0 to.A

... MANUAL VS AUTO SCPAME TYPE NUMEER NUMBER 1995 OF NORMALIZED WEElLY SCRAMS TO 1985 AVERAGE MANUAL SCRAMS O O.O 1.O AUTOMATIC SCRAMS 12 12.O C.4

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REACTOR SCRAM

SUMMARY

WEEK ENDItJG O2/2 /Sr f i FLANT EPECIFIC DATA I.

i COMPLI VTO I DA*E SITE UNIT POWER RPS CAUBE T 012 '.

C AT I O '1 f

95 A EDUIF /M".IN GE NO  !

02/17/Gs EVPON 1 EQUIC/FD VLV NO  !.

02/20/96 SALEM 1 100 A I 100 A EQUIP / BOP YES 1 02/22/E6 WOLF CREEP. EOUIo/TJPF TRP NO 2 02/22/86 DIABLO CANYON 2 90 A NO 2 C2/23/96 f1DRTH AN!'A 1 100 A EDUIP/ POP EUMMARY OC COMPLICATIONS SITE UNIT COMPLICATIONS WOLF CREEV. 1 FEEDWATER LINE LEAV i

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@c6 #< , II.[ COMPARISON'OF JWEEKLY ETATISTICS'W'ITH. INDUSTRY AVERACCS p .s '

A.) :

SCRAMS FOR' WEEK ENDING 02/23/86 5:. %$; u y n-

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Dn: l SCRAM:CA SE - ' POWER- ~ NUMEER . NUMBER L 1 35

< OF' NORMALIZED (6) . WED !,Y SCRAMS (C)- TO'1985 "

AVERASE.

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(3)14) y > ~. .; .  ; ,,..

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it* P.OWER->15% , .. . . . .

"- >15%- 5- Sc0 ;5.4J(69%)?

_ EQUIP._RELATED 4

~  ; -  : PERS.' RELATED (7) >15% 'O , O. O L2.O ( 253. .

LOTHERie) .

.>15% 0 0.O .

O.6 (: 7%

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(, 'O.O 5- 5. O'

, I** POWER'<15%- .. .

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' EQUIP./RELATED

<15% 0 0.O' 1.'3 ' 4 54 % t.

- 'PERS. RELATED~ <15% 0 0.O , 0.9 (CE%):

7 . 'A . ..OTHER, <15% O O.O- O. 2 J( 8%)l 2**, Subtotal **-

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O O.0 1 .2.4 S- e. *** Totals ***-

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. MANUAL.VS AUTO SCRAMS -

1985

$.. NUMEER . NUMBER iTYPE~

OF , . NORMALIZED

• WEEKLY

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AVERAGE; 1 q.a

-TOL1985l SCPAMS' e -

' MANUAL SCRAMS' .O 'O.O .1. O t ' AUTOMATIC SCRAMS -5 5.O 9.4 ,

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.o J - 7 NOTES

-1. PLANT SPECIFIC DATA DASED ON INITIAL REVIEW 0F 50.72 REP 0 HTS ,

FORlTHE WEEK 0F INTEREST. PERIOD.ls MIDNIGHT. SUN'...ThE00GH

" MIDNIGHT SUN SC. RAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLAM EP

' TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE, r

2. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL:EP.RCRS UNRELATED TO CAUSE OF SCRAM 3, 1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS'IN 1985. WEEKLY DATA DETERMINED ~BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY a DIVIDING BY

-52 WEEKS / YEAR

4. IN 1985, THERE WER'E AN ESTIMATED 541 AUTOMATIC 8 MANUAL UN-PLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YlELDS-AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR & AN AVERAGE RATE OF 10.4 TRIPS PER WEEK

~

j' FOR ALL REACTORS. -

5. BASED ON 93 REACTORS HOLDlHG A FULL POWER LICENSE, AS CF 2/1/86

6. NORMALIZED VALUES ALLOW COMPARIS0N TO 1985 DATA BY MULTIPLYING g ACTUAL 1986 VALUE BY: 93 REACTORS IN 1985 NUMBER OF REACTORS REPORTING

7. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL ,

DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROELECS

8. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONhENTAL CAUSES (LIGHTNihG), SYSTEM DESIGN, OR UNKNOWN CAUSE.

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.f 0' ERAT!3 REALTORS EVENT! MEETIN3 FD'.L0d ITEFS AS OF MEETING 86-05 CN FEBRUARY 24,1926^ ".

-(!N ASCEGINS MEETINS DATE, NS$5 '/EN!CP, FACILITY CUER)

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{ ' MEETINS FA0!!!TY REEFCN!! ELE- TASK EESCc!Fi!C% SCdEt7.E C'.0SE!L DATE ' C;r EN'1 k NUP!ER/ NSS5 VE 0 0F/ - DIVI!!;4! : CD*8tET. BY DDCUMEN*,

I -MEETINS EVENTtESCRIF. INDIV!tDal IATE(31 MEETING,ETC.

-SATE 95-13 TEKEY FCINT ; F59!?!LHON'J. 'I / '

FEV!EW ALECUstY OF GCVERCE 03/3)iE6 OcEN-09/13/55 - W -/_PCSI-TRIF . / IESli% CN TLil!NE DDEN Ark -01/05/Ee LO!S OF AFW- PUP 8S !C/13/EF 3: 'B5-21 TROJAN FSB /MILkOAN J REEIAMINE NEED FOR THIS 03/06/96 CLOSED 03/01/26 PE"CRACUM IN 10/23/S$ / IN 08#ECT / INSTA'LATION

. l C SENER!C // MAR:(- ! , 1926 COCG;!CE SETF0!NTSFCR~ AFPLCAE!LITY- / / PE G E. RCE5!

TRIF CF AFW TO 6. h0LAHAN ,

.P!*.F5 CN LCW .

W. SS:TICNFRESSUFE

86 ARKANSA! ! .NRR /r!RABLIA F RE'J!EE B'S!3 FCR FACIL!!Y 0;/31/Ei CFEN / /

01/27/B6 PW / CE51EN ~ /J CRIE!NAL IEIISN MODIFICATICN ./ /

' DEFICIENCYIN A U EAS!! FOR FURTHEF / /

E"EFEEN:V MO:IFICATION tR;F0EEC EV FEEWATER SYSTEM LICENEEE.

86-03 ARTANSAS 1 IE /JCRMN E - IEENTIFY WHAT IS ACTUAL tE!!SN O!/;1/56 CFEN / /

01/27/26 PK / DE3ISN / IN $1E FLANTS //

DEFICIEC Y IN //

'EMERSECY FEEtWATER SYSTEM 86-03 APJAh!A3 1 N"; /M18 AE'.! A F ' DETERMINE GEhERIC A8 PLICA!!LITY C3/31!!L CLCSEC C2/25/96

, O!/27/E6 BK / DES!!N. / Ce AREA %iAE I EESISN IEFICIEh:Y // .FEP. 21 1956

'[ DEFICIECY IN / / OTE F.

7 EMERSECY' M!EASLIA TO G.

y FEEDWaiER SYSTEM HOLAHAN 96-03 'TMI I IE /JCRtAN E CCNS!!ER SUFFLEMENTAL IE N0ilCE 03/31/E6- CFEN / /

, 01/27/96 BW / FARTIAL / 04 RECENT TRIP BREArER FRCBLEMS //

r. LDSS OF NN! //

B6-03 M:GUIRE CHF5/I!! NAN 4 D , /IEW O VEMPER 1, 1955 P:EUIFE 03/31/E6 CFEN /- /

0!/27/06 W / START-U8 / E.'ENT AO LETE*"IEE gr FAILURE //

WITH CESRA D TO REPA!R VALVE MOTOR C'ERATOR / /

HFS! SYSTEM FPICR TO START-Ur hAS IN VIOLATION Cr TECH SPECS ..

REQUIREMENT -

86-04 DRES:EN 3 NRC IEERNER R  !!SOUSS WITH StRS CWNERS S CUF. 03/31/E6 DPEN / /

~ 02/10!!L EE / FIRE IN / THE FRCEAP!LITY CF FCLYUFETHANE //

tRYWCLL

', IGNITING DURIN3 0FERAT!CN A C //

EXPANSIChEAF A8FENt!! R CC"FLI A CE !!!UE

• 86-04 VERMCNT YA EEE IE /ALLISON D CON!! DER IE OT!CE 03/31/86 CLC5ED 02/25/26 02/10/!6 SE / FA! LURE OF / / / IE NOTICE E6-13 STANCSV LIQUID / / SENT FEB. 21, CONTROL SYSTEM - 1936 w