ML20154N875

Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl

ML20154N875
Person / Time
Site:	Dresden, Peach Bottom, Mcguire, Palo Verde, Catawba, Oyster Creek, Arkansas Nuclear, Three Mile Island, North Anna, Turkey Point, Crystal River, Diablo Canyon, La Crosse, McGuire, LaSalle, 05000000, Trojan
Issue date:	03/12/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8603200067
Download: ML20154N875 (21)

Text

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MAR 1219h MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON March 10, 1986 - MEETING 86-07 On March 10, 1986, an Operating Reactor Events meeting (86-07) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on March 3,1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. In addition, the assignment of follow-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclosure 3 with regard to their respective responsibilities.

Note that several assignments are approaching the due date. Please be responsive and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met.

Origind Piped By:

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ encl:

See next page DISTRIBUTION Central Files NRC PDR ORAB Rdg ORAB Members 6

OR RS A , ,

D off:dm RWes man GHolahan q#

3 ////86 J //s./86 / /86 [j,' ,jt 4' ' ' ft 0603200067 860312 ,

PDR ADOCK 05000219 t S PDR

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. Harold R. Denton r 6

4 cc: D. Eisenhut L. Engle i J. Taylor L. Rubenstein C. Heltenes H. Silver j T. Murley, Reg. I J. Stolz i J. Nelson Grace, Reg. II D. Neighbors j J. Keppler, Reg. III K. Johnston i R. D. Martin, Reg. IV S. Varga J. B. Martin, Reg. V D. Mcdonald R. Starostecki, Reg. I R. Woodruff R. Walker, Reg. II K. Jabbour C. Norelius, Reg. III B. J. Youngblood j E. Johnson. Reg. IV

! D. Kirsch, Reg. V i H. Thompson F..Miraglia

R. Bernero T. Speis J W. Russell

T. Novak

! F. Schroeder W. Houston I B. Sheron D. Ziemann  :

! J. Knight D. Crutchfield i G. Lainas V. Benaroya i W. Regan i D. Vassallo E. Jordan

! E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin i

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i . ENCLOSURE 1 LI5T OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-07)

MARCH 10, 1986 NAME DIVISION NAME DIVISION  !

H. R. Denton NRR D. L. Ziemann DHFS

M. J. Virgilio ORAS/NRR V. Benaroya NRR/PWRA W. Haass IE/VPB W. Swenson NRR/0 RAS i W. Regan NRR/PWRB L. Kelly NRR/0 RAS I

M. Poore ORNL D. Vassallo NRR/ DBL C. Miller NRR/PWRB D. Crutchfield NRR/PWRB S. Newberry NRR/0 RAS N. Trehan NRR/ DBL A. Rubin NRR/DSR0 A. Singh NRR/PWRA J. Shapaker NRR/PWRA D. Allison IE/EAB l H. Silver NRR/PWRB S. Diab NRR/DSR0

! F. Rosa NRR/DPA G. Klingler IE/DI '

R. Woodruff IE/DEPER L. Rubenstein NRR/PWRA S. Varga NRR/PWRA D. Mcdonald NRR/PWRA D. Neighbors NRR/PWRA K. Johnston NRR/PWRA J. T. Beard NRR/0 RAS R. Baer IE/DEPER B. Sheron NRR/DSR0 T. Novak NRR/PWRA l R. W. Houston NRR/DCL J. Stolz NRR/PWRB F. Miraglia NRR/PWRB C. E. Rossi NRR/PWRA C. Kniel NRR/GIB D. Tarnoff NRR/0 RAS

L. Engle NRR/PWRA r

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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-07 MARCH 10, 1986 NORTH ANNA UNIT 2 DEGRADATION OF EMERGENCY DIESEL GENERATORS 2H 8 2J CRYSTAL RIVER UNIT 3 REACTOR COOLANT PUMP FAILURES - UPDATE TROJAN MULTIPLE FAILURES OF AUXILIARY FEEDWATER FLOW CONTROL VALVE COUPLINGS, BOTH TRAINS i TURKEY POINT UNIT 3 INADEQUATE COMPONENT COOLING WATER FLOW TO EMERGENCY CONTAINMENT COOLERS OTHER EVENTS OF INTEREST TURKEY POINT 3 AND 4 SEISMIC PROBLEMS WITH ACCUMULATOR FILL LINES CATAWBA UNIT 1 LOSS OF BOTH TRAINS OF SAFETY-RELATED CONTAINMENT ISOLATION SEAL WATER INJECTION  !

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l NORTH ANNA UNIT 2 - DEGRADATION OF EMERGENCY DIESEL GENERATORS 2Hg2J

MARCH 4, 1986 (L. B. ENGLE, NRR)

PROBLEM:

SCHEDULED INSPECTION OF EDG 2H DURING CURRENT REFUELING OUTAGE j INDICATES DEGRADATION OF PISTON PIN BUSHINGS.

j EDG 2J (NOT YET INSPECTED) DETERMINED TO HAVE BEEN INADVERTENTLY

OVERLOADED DURING 24-HOUR SURVEILLANCE TEST.

SIGNIFICANCE:

EDG VENDOR ATTRIBUTES 2H BUSHING ELONGATION T0 " ENGINE OVERLOAD CAUSED FROM EXCESSIVE NUMBER OF FAST STARTS, UNEQUAL FIRING PRESSURE, TIMING AND ELECTRICAL OVERLOADING" 0F GENERATOR.

1 l DISCUSSION:

i EDG "H" BUSHINGS REPLACED DURING OCTOBER 1985 0UTAGE FOLLOWING l ENGINE FAILURE.

} EDG "H" HAD ONLY 3 FAST STARTS SINCE OCTOBER 1985 0UTAGE.

TOTAL RUN TIME FOR EDG "H" SINCE OCTOBER OUTAGE APPR0XIMATELY j 80 HOURS.

EDG "J" DETERMINED TO HAVE BEEN INADVERTENTLY OVER-LOADED TWICE IN EXCESS OF 2900 - 3000 Kw FULL LOAD TEST.

i FOLLOWUP: '

LICEN E L CENSEE'S INDEPENDENT CONSULTANT, VENDOR, REGION II AND

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. NORTH ANNA UNIT 2 2H EMERGENCY DIESEL GENERATOR

SUMMARY

OF MOST SIGNIFICANT FINDINGS AND ACTIONS DURING ONG0ING EDG 2H INSPECTION AND OVERHAUL:

NINE (9) PISTONS SHOWED SIGNS OF CHROME SCRATCHING ON THE CROWN AND SLIGHT PITTING DUE TO FUEL IMPINGEMENT, PISTONS WERE REPLACED, FOUR (4) PISTON WRIST PIN BUSHINGS WITH SCRATCHES WERE REPLACED, THIRTEEN (13) PISTON PIN (FLOATING) BUSHINGS WERE REPLACED, FIVE (5) 0F THE BUSHINGS WERE EXTRUDED BY 0.003, 0.008, 0,018, 0.023, AND 0.032 INCHES BEYOND THE ACCEPTABLE UPPER LIMIT OF 3,187 INCHES, ONE MAIN BEARING SHOWED SIGNS OF SCORING AND WAS REPLACED, ALL OTHER BEARINGS GOOD AND REINSTALLED, ALL CONNECTING RODS AND R0D BEARINGS LOOKED GOOD AND WERE REINSTALLED, TEN (10) CYLINDER LINERS REPLACED WITH LINERS WITH HIGH TEMPERATURE SEALS, REMAINING TWO (2) CYLINDER i LINERS INSTALLED IN OCTOBER 1985 WITH HIGH TEMPERATURE j

SEALS, LINERS REMOVED IN GOOD CONDITION, BUT EXHIBITED SIGNS OF PORT CARB0NING DEPOSITS, ALL COMPRESSION AND DIL RINGS WERE IN GOOD CONDITION, TEN (10) SETS OF RINGS WERE REPLACED IN THE CORRES-PONDING NEWLY INSTALLED LINERS, CONNECTING R0D BOLTS AND NUTS INSPECTED PER RECENT i

PART 21 NOTIFICATION BY DIESEL MANUFACTURER, AND 50% WILL BE REPLACED, 1

4

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,- NORTH ANNA - UNIT 2 2J EMERGENCY DIESEL GENERATOR EARLY IN UNIT 2 REFUELING OUTAGE TS REQUIRED THE PERFORMANCE OF THE 24-HOUR LOAD TEST.

24-HOUR TEST INCLUDED REQUIRED TWO HOUR RUN AT 2900 - 3000 Kw. )

DURING 2-HOUR TEST THE EDG 2J WAS DETERMINED TO HAVE EXPERIENCED TWO EXCURSIONS IN EXCESS OF 3000 Kw. )

THE EDG 2J WAS OVERLOADED FOR 7-1/2 MINUTES AT 3200 Kw AND l-1/2 MINUTES AT 3450 Kw.

REGION II HAS CITED THE LICENSEE FOR NOT FOLLOWING APPROVED PROCEDURES WHICH LED TO INADVERTENT OVER-  ;

LOADING.

THE DG 2J IS SCHEDULED FOR INSPECTION AND OVERHAUL  ;

COMMENCING WEEK 0F MARCH 10 - 14, 1986.

AN ON-SITE MEETING WITH REGION II AND NRR IS SCHEDULED FOR MARCH 19, 1986.

NRC STAFF WILL INSPECT EDG 2J PARTS IN MORNING AND MEET WITH LICENSEE, CONSULTANTS, AND VENDOR AFTER INSPECTION.

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- BASED ON THE AB0VE, THE LICENSEE IS EVALUATING THE EDG J RELIABILITY AND MAINTENANCE WORK PRACTICES.

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CRYSTAL RIVER UNIT 3 - REACTOR COOLANT PUMP FAILURES JANUARY 1, 1986 UPDATE (H. SILVER, NRR)

PROBLEM:

MULTIPLE REACTOR COOLANT PUMP (RCP) SHAFT AND BOLT CRACKS J

SIGNIFICANCE:

RCP FAILURES, SEAL FAILURES, AND CHALLENGE TO SAFETY SYSTEMS PROBABLE GENERIC PROBLEM CIRCUMSTANCES:

RCPs AT CRYSTAL RIVER-3 ARE BYRON JACKSON PUMPS AFTER 1/1/86 TRIP, RCP "A" SHAFT FOUND BROKEN WITHIN HYDR 0 STATIC BEARING. FATIGUE CRACK INITIATED IN GROOVE CAUSE UNCERTAIN, BUT MAY BE COMBINATION OF DESIGN, MANUFACTURING, RESIDUAL STRESSES, BENDING, AND THERMAL CYCLING l OTHER 3 PUMPS ULTRASONIC TESTED - INDICATIONS FOUND ON ALL SHAFTS "B" SHAFT REMOVED - CRACK NEAR IMPROPER WELD "C" AND "D" PUMPS TO BE DISASSEMBLED CRACKED SHAFTS TO BE REPLACED, PUMP VIBRATION MONITORS TO BE UPGRADED ALL 8 CAP BOLTS AND 5 0F 8 TOROVE PINS CRACKED ON "A" AND "B" PUMPS.

OTHERS TO BE EXAMINED AND REPLACED FOLLOWUP:

PLANT REMAINS SHUTDOWN; REPAIRS EXPECTED TO BE COMPLETE IN JUNE INSPECTION REPORT DUE OUT S00N

{ LICENSEE WILL MAKE PRESENTATION TO NRC IN APRIL l PLANTS WITH IDENTICAL PUMPS (DAVIS-BESSE AND ARKANSAS-1)

HAVE BEEN COORDINATING WITH CRYSTAL RIVER-3.

IE INFORMATION NOTICE BEING ISSUED I

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TROJAN - MULTIPLE FAILURES OF AUXILIARY FEEDWATER FLOW CONTROL VALVE COUPLINGS, BOTH TRAINS MARCH 3, 1986 (K JOHNSTON, NRR)

PROBLEM:

FAILURE OF MOTOR-TO-VALVE COUPLING ON 3 0F 4 "A" TRAIN AND 1 0F 4 "B" TRAIN AUXILIARY FEED FLOW CONTROL VALVES, SIGNIFICANCE:

POTENTIAL FOR CONTROL VALVES TO NOT SERVE THEIR FUNCTION, I.E.,

STEAM GENERATOR LEVEL CONTROL AND FEEDWATER LINE ISOLATION, DISCUSSION:

ONE TRAIN "A" VALVE WAS BEING REPACKED, "A" TRAIN INOPERABLE, WHILE MANUALLY BACKSEATING VALVE, THE COUPLING FAILED, DURING SUBSEQUENT INSPECTIONS OF THE OTHER 3 "A" TRAIN CONTROL VALVE COUPLINGS, ONE WAS FOUND LOOSE, ANOTHER WAS FOUND MISALIGNED, NEXT DAY, "B" TRAIN WAS DECLARED INOPERABLE TO INSPECT VALVES; THE PLANT WAS BROUGHT FROM 100% TO 35% POWER PER TECH, SPECS, ONE "B" TRAIN COUPLING WAS FOUND MISALIGNED, "A" TRAIN COUPLINGS REPAIRED AND TRAIN DECLARED OPERABLE, MARCH 6 - TROJAN RETURNED TO 100% POWER, FOLLOW-UP:

CAUSE OF FAILURE WAS P00R ALIGNMENT OF COUPLING, i

REGION V IS FOLLOWING UP ON PAST MAINTENANCE OF FLOW CONTROL VALVE COUPLINGS AND COUPLING INSTALLATION AND DESIGN, NRR IS FOLLOWING UP REGARDING THE GENERIC IMPLICATIONS,

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TURKEY POINT UNIT 3 - INADEQUATE COMPONENT COOLING WATER FLOW TO EMERGENCY CONTAINMENT COOLERS MARCH 4, 1986 (D. MCDONALD, NRR)

PROBLEM:

CONTINUING COMPONENT COOLING WATER (CCW) PROBLEMS.

! SAFETY SIGNIFICANCE:

l INADEQUATE FLOW THROUGH THE THREE EMERGENCY CONTAINMENT COOLERS 1 (ECC) UNDER DESIGN BASIS CONDITIONS.

1 ADEQUACY OF DESIGN BASIS OF CCW SYSTEM.

CIRCUMSTANCES:

1 UNIT 3 AT 95% POWER AND UNIT 4 IN REFUELING.

INADEOUATE ECC FLOW IDENTIFIED DURING UNIT 4 TESTS PERFORMED TO VERIFY REPOSITIONING OF RHR HEAT EXCHANGER DISCHARGE VALVES (30% TO 100% OPEN).

UNIT 4 TESTS PERFORMED, 1 CCW PUMP (MARCH 3 & 4) DISCHARGE VALVES.

30% OPEN: RHR 2800-3800 GPM (4000 GPM REQUIRED)

ECC 4850 GPM (6000 GPM REQUIRED) 100% OPEN: RHR 8438-8785 GPM ECC 2800 GPM l REMOVING NON-ESSENTIAL LOADS INCREASES ECC FLOW TO APPROXIMATELY 4

3300 GPM.

DECLARED UNIT 3 ECC INOPERABLE AND COMMENCED SHUTDOWN.

FOLLOWUP:

l UNIT 3 TESTS ON 1 CCW PUMP (MARCH 7) DISCHARGE VALVES

30% OPEN

RHR 3180-3600 GPM (4000 GPM REQUIRED)

ECC 6000 GPM (6000 GPM REQUIRED)

INFORMED NRC 0F CCW FLOW BALANCE TESTS.

i R-II AND NRR PERSONNEL ON-SITE TO ASSESS TEST PROCEDURES AND RESULTS PRIOR TO STARTUP.

APPR0XIMATELY 42% OPEN POSITION APPEARS TO PROVIDE ADEQUATE CCW FLOW TO ALL COMPONENTS.

R-II ASSESSING ACCEPTABILITY,

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OTHER EVENTS OF INTEREST

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! TURKEY POINT 3 AND 4 - SEISMIC PROBLEMS WITH ACCUMULATOR FILL LINES l NOVEMBER, 1985 (R, WOODRUFF IE) 1 PROBLEM ACCUMULATOR FILL LINE IS NOT SEISMIC.

ACCUMULATORS REQUIRE FREQUENT MAKEUP l ISOLATION VALVE (NORMALLY CLOSED) IS 15% OPEN HPSI PUMP IS OPERATED AT LOWER THAN RECOMMENDED FLOW ,

I SIGNIFICANCE MARGINAL OPERATION AND MAINTENANCE CIRCUMSTANCES

NSSS VENDOR ORIGINALLY INTENDED FILL LINE TO BE SEISMIC I LICENSEE REVIEW DETERMINED LINE NOT TO BE SEISMICALLY INSTALLED.

l FOLLOWUP i REGION II: COMPLETE REVIEW 0F LICENSEE'S 50.59 REVIEW OBTAIN COMMITMENT TO REPAIR ACCUMULATOR LEAKS

CLOSE ISOLATION VALVE i

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CATAWBA UNIT 1 - LOSS OF BOTH TRAINS OF SAFETY-RELATED CONTAINMENT ISOLATION SEAL WATER INJECTION SYSTEM MARCH 7, 1986 (K. N. JABBOUR, NRR)

PROBLEM:

SAFETY-RELATED WATER SOURCE FOR BOTH TRAINS OF CONTAINMENT ISOLATION SEAL WATER INJECTION SYSTEM WAS LOST FOR 12 HOURS BECAUSE OF VALVE TESTING. NORMAL SOURCE WAS AVAILABLE.

SIGNIFICANCE:

POTENTIAL FOR RELEASE VIA AFFECTED PENETRATIONS, DISCUSSION:

LICENSEE'S PERSONNEL ISOLATED BOTH TRAINS OF THE SAFETY-RELATED WATER SOURCE (I.E., NUCLEAR SERVICE WATER SYSTEM) TO PERFORM STROKE TIMING TESTS ON VALVES IN EACH TRAIN, BECAUSE THE NORMAL SUPPLY TO THE SEAL WATER INJECTION SYSTEM WAS OPERABLE, THE OPERATORS WERE NOT AWARE OF THE ASSURED SOURCE LOSS UNTIL 4 HOURS AFTER ISOLATION VALVES WERE REOPENED, ROOT CAUSE:

PERSONNEL ERROR FAILURE TO FOLLOW PROCEDURE POOR TEST COORDINATION FOLLOWUP:

LICENSEE INSTRUCTED PERSONNEL TO FOLLOW PROCEDURES,

r REACTOR SCRAM

SUMMARY

WEEK ENDING 03/09/86 I. PL. ANT E.PECIFIC DATA DATE SITE UNIT POWER PPS CAUSE COMPLI- YTP CATIONS TOTAL 03/03/86 LASALLE 2 8A PERSONNEL NO

• 2 03/05/86 TURKEY POINT 3 OA EQUIP /SR INSTR NO 2 03/OS/e6 01AetO CnNv0N  : 300 A EDU1e/POo CTRt NO 3 03/06/86 OYGTER CREEU 1 91 A PEREONNEL YES 1 03/06/86 PEACH BOTTOM 3 2A PERSONNEL NO 1 18 A EQUIP /MFP NO 4 03/07/86 PALO VERDE 1 03/07/86 LACROCEE 1 - 72 A EQUIP /SWYRD YES 2

SUMMARY

OF COMPLICATIONS EITE UNIT COMPLICATIONS OYSTER CREEV 1 CONTAINMENT ' SOLATION AND EMERGENCY CONDENSOR ACTUATION LACROSSE 1 1 CPD DIE NOT FULLY INEERT l

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II. COMPARISON OF WEEKLY STATIETICS WITH INDUSTRY AVEFf,GE9 SCRfiMS FOR WEEK ENDING 03/09/86 SCRAM CAUSE POWEP NUMEEP NUMBER ,

1985 OF NORMALIZED (6) WEEKLY ECRAME(5) TO 1985 AVERAGE

. (3) (4 )

• • POWER 15%

EOUIP. RELATED >15% e. v.O 5.4 (69%)

PERS. RELATED(7) >15% 1 1.0 2.0 (25%)

OTHER(9- 3157. O O.O O.6 ( 7.)

• • Subtotc1 **

4 4.0 8.0

• • POWER <157 EQUIP. RELATED < i3% 1 1.0 1.3 (54%)

PERS. RELATED '5% -

. .O O.9 (38%)

OTHER :13% 0 0.0 0.2 ( 8%)

• • Subtotz1 44 3 3.0 2.4

• tt Total ***

7 7.0 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBFR NUMBER 1985 OF NORMALIZED WEEKLY SCRAMS TO 1985 AVERAGE MANUAL SCRAMS O O.0 1.0 AUTOMATIC SCRAMS 7 7.0 9.4 i

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NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUN. THROUGH MIDNIGHT SUN. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A l PLANT PROCEDURE.

2. RECOVERY LOMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS 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 8 DIVIDING BY 52 WEEKS / YEAR

4. IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC a MANUAL UNPLANNED 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 FOR ALL REACTORS.

- 5. BASED ON 93 REACTORS HOLDING A FULL POWER LICENSE, AS OF 2/1/86

6. NORMALIZED VALUES ALLOW COMPARIS0N TO 1985 DATA BY MULTIPLYING 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 PROBLEMS

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

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ENCLOSURE 3  :

Page N:. 1 i

l CPERATING REACTORS EVENTS MEETIN6 FOLLOWUP ITEMS AS OF MEETING 86-07 CN MARCH 10 , 1986 (IN ASCENDING MEETINS DATE, NSSS VENDOR FACILITY ORDER)

• GEEVINS FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED CATE CORMENTS NUM!ER/ NSSS VENDOR / DIVIS!CN! COMPLET. BY DOCUMENT, l MEETING EVENT DESCRIP. INDIVILL'AL DATE(S) MEETING,ETC.  !

DATE B5-13 TURkEi FOINT ! PSE /MILH0AN J . FEVIEW ADEQUACY OF GOVERNOR 03/30/06 0 FEN / /  !

08/13/25 W / POST-TRIF / DESIGN ON TURBINE DRIVEN AFW 01/05/86 LOSS OF AFW FUFFS 10/13/85 86-03 AffANSAS 1 V R IMIRAGLIA F EEV!EW IASIS FOR FACILITI 03/31/86 0 FEN //

01/27/E6 SW / DESIGN / ORIGINAL IESIGN MODIFICATION / / '

DEFICIEN:Y IN A G BASIS F0F FURTHEP / /  ;

ENEFSEN:) MODIFICATION FROFDSED BV  ;

FEE dTER SYSTEM LICENSEE.

l B6-03 AFWANSAS 1 *E ! JORDAN E IDENTIFY WHAT IS ACTUAL DESIEN 03/31/26 0 FEN / / [

Cl!27!E6 EW / DESIGN / IN B&W FLANTS // '

LEFICIENCf IN / /  ?

EMERSEN:)

FEECWATER SYSTEM 26-03 TMI 1 MR />0LAHAN 6 CONSIIER SUFPLEMENTAL IE NOTICE 03/31/26 0FEh / /

01/27/E6 ik / FAFT!AL IE /J0RDAN E ON FECENT TRIP B;EA>EE FR09LEMS //

LOSS OF NNI / /

GH3 M:SU!FE D-FSIZIE%% D REVIEW NSVEM!EF 1, 1985 M:6UIRE 03/31/86 OPEN / /

01/27/E6 W / STAF.T '? / EVENT AND DETERMINE IF FAILUFE / /

WITH DEGRALED TO REFAIR VALVE MOTOR OFERATOR // 1 HPSISiiTEM FR10; TO START-UP WAS IN VIOLATION 0F TECH SFECS

EQUIREMENT 4 66-04 0FESDEN 3 hEF /BEB ERO R DISCUSS WITH BhRS OWNERS GROUP 03/31/E6 OPEN / /

02/10/E6 GE / FIFE IN / THEFR0EA21LITYOFPOLYURETHANE / / ,

DRYWELL IGNITING DURING 0FERATION AND / / f EIFANS!0N6AP AFFEND11 R COMPLIANCE ISSUE 86-06 TUFFEY PDINT 3 NRR /HDLAHAN 6. SCHEDULETURKEYPOINTFOLLOWUP 03/15/86 CLOSED 03/10/96 PRESENTATION 03/03/06 W / COMP 0NENT / PRESENTATIONBEFORE 03/18/86 // PRESENTATIDNON SCHEDULED FOR C00 LINS WATEF / / 03/10/86 03/10/96 SYSTEM VALVES MISPOSITIChED FOR LIFE OF PLANT 86-06 W PLANTS IE /JDRDAN E REVIEW REFORTABILITY OF ITEMS 03/20/86 OPEN / /

03/03/96 W / SINSLE / SUCH AS SINGLE FAILURE OF P-10 // i FAILURE OF INTEFLOCK // h

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