ML20155F194
| ML20155F194 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Dresden, Pilgrim, Summer, Brunswick, River Bend, Quad Cities, Rancho Seco, FitzPatrick, 05000000, Fort Saint Vrain |
| Issue date: | 04/10/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8604210401 | |
| Download: ML20155F194 (20) | |
Text
-
m APR 1 0 1986 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUPetARY OF THE OPERATING REACTORS EVENTS MEETING ON APRIL 7, 1986 - MEETING 86-11 On April 7,1986, an Operating Reactor Events meeting (86-11) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on March 31, 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 ORAS (D. Tarnoff, x27864) if the target completion date cannot be met.
A//
Gary M. Holahan, Director Operating Reactors Assessment Staff Distribution
Enclosures:
Central Filev/
As stated 888, d ',k# }
ORAS Rdg
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cc w/ encl:
D. Tarnoff See next page R. Wessman
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PDR ADOCK 05000237 S
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APR 10E86 Harold R. Denton cc:
D. Eisenhut E. Sylvester J. Taylor D. Muller C. Heltemes S. Stern T. Murley, Reg. I W. Butler J. Nelson Grace, Reg. II R. Gilbert J. Keppler, Reg. III J. Zwolinski R. D. Martin, Reg. IV H. Bailey J. B. Martin, Reg. V S. Miner R. Starostecki, Reg. I J. Stolz-R. Walker, Reg. II R. Auluck C. Norelius, Reg. III G. Kalman E. Johnson. Reg. IV D. Kirsch, Reg. V H Thompson F. Miraglia R. Bcrnero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin J
3 1
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-11)
\\~
April 7,1986 NAME DIVISION NAME DIVISION G.-M. Holahan NRR/0 RAS G. Lainas NRR/ DBL J. T. Beard NRR/0 RAS E. Rossi NRR/PWR-A M. J. Virgilio NRR/0 RAS D. Humenansky OCM/LZ R. A. Gilbert NRR/BWD #1 C. Ader OCM D. Tarnoff NRR/0 RAS F. Schroeder NRR/DPL-B R. W. Woodruff IE/VPB B. Sheron NRR/DSR0 D. R. Muller NRR/BWD #2 J. Zwolinski NRR/ DBL /BWD #1
'W. P. Haass IE/VPB E. Sylvester NRR/ DBL S. C. Rhow EICSB/BL R. Auluck NRR/ DBL W. H. Swenson NRR/0RPW A.- D'. Kimins ORNL/NOAC D. B. Vassallo NRR/ DBL W. H. Regan NRR/PWR-B D. L. Ziemann DHFT D. Crutchfield NRR/PWR-B R. C. Jones NRR/PWR-B E. J. Weinkam NRR/PWR-A H. Bailey-IE/EAB E. Weiss IE/EAB R. Hernan NRR/PPAS S. Stern NRR/ DBL M. Chiramal AEOD S. Rubin AE00 E. Jordan IE R. Frahm' NRR/SPEB R. Baer IE/DEPER
OPERATING REACTORS EVENTS BRIEFING 86-11 APRIL 7, 1986 BRUNSWICK UNIT 1 MULTIPLE BREAKER FAILURE RIVER BEND MAIN STEAM LINE LEAKAGE CONTROL SYSTEM INOPERATIVE DRESDEN UNITS 2 AND 3 SHUTDOWN OF UNIT 2 WHEN CONTROL ROOM PANELS FOUND NOT SEISMICALLY QUALIFIED RANCHO SECO CLASS 1E STATION BATTERY PROBLEMS MONTICELLO POTENTIAL LOSS OF BOTH ELECTRIC POWER DIVISIONS DUE TO HIGH ENERGY LINE BREAK (HELB) i OTHER EVENT OF INTEREST RANCHO SECO DEAD C0WS; UNRELATED OFFSITE CONTAMINATION
BRUNSWICK UNIT 1 - MULTIPLE BREAKER FAILURE APRIL 2, 1986 (E. SYLVESTER, NRR)
PROBLEM:
SPURIOUS TRIP 0F FEEDER BREAKER TO ONE 4160V BUS FROM UNIT AUXILIARY TRANSFORMER, WITH SUBSEQUENT FAILURE OF FEEDER BREAKER FROM STARTUP TRANSFORMER.
SIGNIFICANCE:
NO IMMEDIATE TRANSFER TO 0FFSITE POWER.
INABILITY TO SECURE EMERGENCY DIESEL GENERATOR (EDG) DURING RECOVERY OPERATIONS, AS RESULT OF INTERACTION BETWEEN ONSITE AND OFFSITE POWER SOURCES.
DISCUSSION UNIT 1 AT 60% POWER (1 FEEDWATER TRAIN IN MAINTENANCE)
FEEDER BREAKER FROM UNIT AUXILIARY TRANSFORMER TO BUS ID TRIPS NO IMMEDIATE TRANSFER TO OFFSITE POWER RESULTANT LOSS OF POWER TO EMERGENCY BUS El AND AUT0-START AND LOAD OF EDG 1.
LOSS OF BUS 1D; CONDENSATE 8 CONDENSATE B0OSTER PUMPS CAUSED FEEDWATER PUMP TRIP, SCRAM DUE TO LOW WATER LEVEL.
AFTER TURBINE-GENERATOR TRIP, FEEDER BREAKER FROM STARTUP TRANSFORMER CLOSES; BUS ID NOW FED FROM OFFSITE POWER.
ALL SAFETY SYSTEMS OPERATE AS DESIGNED PLANT RECOVERY STARTED.
ATTEMPTS TO SECURE EDG 1 FAIL EDG 1 OUTPUT BREAKER INTERLOCK SUCH THAT OUTPUT BREAKER CANNOT BE OPENED IF BOTH OFFSITE FEEDER BREAKERS ARE OPEN; BREAKER FROM STARTUP TRANSFORMER IWDICATED OPEN.
MECHANICAL LINKAGE."f.! LURE TO POSITION SWITCH FOLLOW-UP:
FEEDER BREAKER FROM AUX. TRANSFORMER - DIAGNOSTICS SHOW FAILURE OF BREAKER; CAUSE NOT DETERMINED FEEDER BREAKER FROM STARTUP TRANSFORMER - REPAIPED, ALL SIMILAR SWITCHES INSPECTED, 3 MORE LOOSE CONNECTIONS REPAIRED
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RIVER BEND - MAIN STEAM LINE LEAKAGE CONTROL SYSTEM IN0 PERATIVE APRIL 2, 1986 (S. STERN)
PEORLEM:
ONE FLOW CONTROLLER FOR THE MAIN STEAM LINE POSITIVE VALVE LEAKAGE CONTROL SYSTEM INOPERATIVE DUE TO INADEQUATE MAINTENANCE PROCEDURES.
SIGNIFICANCE:
NO POSITIVE CONTROL OF LEAKAGE PAST ONE OF THE MSIV'S IN EACH STEAM LINE.
INCREASED 0FFSITE DOSE RELEASES DURING A LOCA, IF THE REDUNDANT VALVE WERE ALSO TO FAIL.
POTENTIALLY INADE0UATE MAINTENANCE PROCEDURES AND POST MAINTENANCE TESTING.
DISCUSSION:
l POSITIVE LEAKAGE CONTROL SYSTEN PRESSURIZES THE SPLIT GATES AND STEMS OF THE MSIV VALVES WITH AIR TO REDUCE LEAKAGE PAST l
THE VALVES DURING A LOCA.
OF TWO INDEPENDENT SYSTEMS (ONE FOR INBOARD AND ONE FOR OUTB0ARD l
MONTHLY SURVEILLANCE TEST SHOWED POSITIVE LEAKAGE CONTROL SYSTEM FOR ONE MSIV IN EACH STEAM LINE TO BE IN0PERABLE.
PREVIOUSLY OPERABLE DURING MARCH 3, 1986 SURVEILLANCE TEST MAINTENANCE PERFORMED IN MID-MARCH DURING APRIL SURVEILLANCE TEST, DISCOVERED WIRE CONNECTED TO WRONG TERMINAL WIRE RE-CONNECTED TO CORRECT TERMINAL AND SYSTEM DETERMINED TO BE OPERABLE WITHIN 24 HOURS FOLLOWING DISCOVERY.
FOLLOWUP:
LICENSEE IS INVESTIGATING WHEN AND HOW THIS OCCURRED AND WILL REPORT IN LER.
LICENSEE WILL TAKE CORRECTIVE ACTION ONCE SOURCE OF PROBLEM DETERMINED.
REGION CONSIDERING CONFERENCE WITH UTILITY.
NRR PM TO FOLLOW-UP LICENSING ISSUES.
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p DRESDEN UNITS-2 AND 3 - SHUTDOWN OF UNIT 2 WHEN CONTROL ROOM PANELS FOUND NOT SEISMICALLY QUALIFIED APRIL 1, 1986'(R. A. GILBERT, NRR)
PROBLEM:
BOLTS REQUIRED TO HOLD DOWN PANELS NOT INSTALLED PER DESIGN. DRAWINGS FOR BOTH UNITS f
SIGNIFICANCE:
POTENTIAL MOVEMENT OF PANELS DURING SEISMIC EVENT
[
ALL CONTROL ROOM PANELS'AFFECTED.
UN-NOTICED FOR 16 YEARS OF OPERATION.
L-DISCUSSION
~*
LICENSEE ENGINEERS WORKING ON DETAILED CONTROL ROOM DESIGN REVIEW MODIFICATIONS NOTED PROBLEM LICENSEE CONFIRMED THAT THE "AS-BUILT" CONFIGURATION DID NOT u
CONFORM TO DESIGN DRAWINGS (SEE " PROBLEM" AB0VE)
INITIALLY,-SARGENT AND LUNDY PERFORMED A " FRICTIONAL FORCE" ANALYSIS TO SEE IF PANELS ARE SEISMICALLY QUALIFIED "AS IS" AFTER EVALUATING THIS ANALYSIS, LICENSEE IMMEDIATELY DECIDED T0 INSTALL BOLTS (WELD WHERE NEEDED).
LICENSEE THEN DECLARED AN UNUSUAL EVENT, NOTIFIED THE RESPONSE CENTER AND SHUT DOWN UNIT 2.
UNIT 3 IN PIPE REPLACEMENT OUTAGE REGION III APPROVED RESTART OF UNIT 2.
FOLLOW-UP:-
SARGENT AND LUNDY CONDUCTING CONFIRMATORY ANALYSIS OF REVISED l
AS-BUILT CONFIGURATION TO SEE IF IT MEETS SEISMIC REQUIREMENTS.
REPORT DUE IN 10-14 DAYS REGION III WILL EVALUATE.
COPY WILL BE SENT TO NRR I
RANCHO SEC0 - CLASS lE STATION BATTERY PROBLEMS MARCH 28, 1986 (H. BAILEY, IE)
PROBLEM:
EXTENSIVE EROSION (FLAKING) INSIDE BATTERY NEAR THE TOP 0F THE PLATES BETWEEN THE PLATES AND THE PLATE SUPPORTS.
BATTERY SPACING IS INCORRECT.
SIGNIFICANCE:
CLASS 1E STATION BATTERIES NOT SEISMICALLY QUALIFIED: POTENTIAL FOR LOSS OF ALL DC POWER DURING SEISMIC EVENT.
DISCUSSION:
EROSION PROBLEM DISCOVERED BY BATTERY VENDOR (GNB) IN FEBRUARY 1986.
PRESENT TECH SPEC SURVEILLANCES WOULD NOT REVEAL THIS PROBLEM.
VENDOR REPORTS THIS EROSION IS NOT UNUSUAL FOR A "PLANTE" TYPE BATTERY MORE THAN 15 YEARS OLD.
BATTERIES DID NOT SHOW SIGNIFICANT EROSION 1 YEAR AGO DURING VENDOR INSPECTION.
BATTERY-T0-RACK AND CELL-TO-CELL SPACING ALSO FOUND TO BE OUT OF DESIGN SPECIFICATIONS.
VENDOR INFORMED LICENSEE THAT BATTERIES WERE NOT SEISMICALLY QUALIFIED, DUE TO IMPROPER BATTERY-TO-END-RACK SPACING.
SOME SPACING HAS BEEN CORRECTED.
FOLLOWilP:
ADEQUACY OF LICENSEE'S BATTERY SURVEILLANCE PROGRAM IS UNDER REVIEW BY REGION V.
CONCERNS INCLUDE THE RATED LOAD TEST AT EACH REFUELING AS WELL AS EROSION PROBLEM.
SOME COMMONWEALTH EDISON COMPANY PLANTS WERE REPORTED TO HAVE THE SAME TYPE BATTERY AND CECO IS REPORTED TO BE REPLACING THEM.
RANCHO SECO PLANS TO REPLACE THE "PLANTE" (LEAD) TYPE BATTERIES WITH A LEAD-CALCIUM TYPE BATTERY.
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MONTICELLO - P0TENTIAL LOSS OF BOTH ELECTRIC POWER DIVISIONS DUE TO HIGH ENERGY LINE BREAK (HELB)
MARCH 27, 1986 (R. AULUCK, NRR)
PROBLEM:
HELB ANALYSIS DID NOT INCLUDE PIPE CHASE ROOM IN TURBINE BUILDING.
SIGNIFICANCE:
A GUILLOTINE BREAK WILL OVERPRESSURIZE THE PIPE CHASE ROOM AND DAMAGE THE WALLS AND AFFECT THE PLANT'S ECCS CAPABILITY.
POSTULATED BREAK REQUIRES PRE-EXISTING PIPE CRACK AND SEISMIC EVENT.
POTENTIAL GENERIC APPLICABILITY TO OTHER PLANTS OF THIS ERA.
DISCUSSION:
PLANT LICENSED 1970; NEW HELB ANALYSIS 1972-1973.
LICENSEE INFORMED THE RESIDENT THAT A FEEDWATER LINE BREAK IN THE PIPE CHASE ROOM WAS NEVER ANALYZED.
ON APRIL 4, 1986, THE LICENSEE INFORMED REGION III THAT A GUILLOTINE BREAK OF THE FW LINE IN THAT ROOM WILL OVER-PRESSURIZE THE ROOM AND DAMAGE THE WALLS.
POSSIBLE DAMAGE TO THE DIV, 2 MOTOR CONTROL CENTERS ADJACENT TO THE ROOM AND DIV 1 ELECTRICAL CABLE'd INSIDE THE ROOM.
REGION.III CONFERRED WITH NRR-PM REGARDING CONTINUED PLANT OPERATION ; PLANT IS AT ABOUT 70% POWER AND C0ASTING DOWN FOR REFUELING SHUTDOWN ON APRIL 30, 1986.
FRACTURE MECHANICS ANALYSIS FOR THE FW SYSTEM CURRENTLY UNDERWAY (BASED Oh DYNAMIC SEISMIC ANALYSIS AND RELIANCE ON " LEAK BEFORE BREAK") EXPECTED TO SHOW THAT GUILLOTINE PIPE BREAK IN THIS ROOM IS UNLIKELY.
EARLY ANALYSIS OF HELBs MAY NOT HAVE CONSIDERED ALL " SERIOUS BREAK" LOCATIONS.
FOLLOWUP:
LICENSEE COMPENSATORY MEASURES:
MONITOR THE PIPE CHASE ROOM TWICE PER SHIFT WILL SHUTDOWN IF ANY LEAKAGE IS FOUND DESIGN MODIFICATION WILL BE COMPLETED DURING THE REFUELING OUTAGE.
GENERIC ACTION:
BEING DEVELOPED.
NRR STAFF TO REVIEW ANALYSIS FOR CONTINUED OPERATION THROUGH APRIL 30, 1986.
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5 0THER EVENT OF INTEREST RANCHO SEC0 - DEAD C0WS; UNRELATED OFFSITE CONTAMINATION MARCH 24 - 28, 1986 (G. KALMAN, NRR) g' PROBLEM:
FOUR C0WS FOUND DEAD ON GRAZING LAND CONTAMINATED BY
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RANCHO SECO EFFLUENTS SIGNIFICANCE:
COW DEATHS UNRELATED TO CONTAMINATION
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0FFSITE CONTAMINATION IS A SITE SPECIFIC AND POTENTIALLY GENERIC PROBLEM.
DISCUSSION:
C0WS TRAPPED, DEHYDRATED IN EQUIPMENT STORAGE PEN.
j NRC ENVIRONMENTAL CONTAMINATION REPORT TO BE RELEASED THIS WEEK.
1.
RANCHO SECO LIQUID EFFLUENTS DURING 1980 - 1984 CONTAMINATED
[
ENVIRONMENT.
2.
POTENTIAL FOOD PATHWAY DOSE - 40 MR/YR. (33-47 MR/YR.)
3.
POTENTIAL RESIDENCE DOSE - 90 MR/YR.
4.
NO DETECTABLE EXPOSURE TO WORST-CASE OFFSITE CITIZEN.
f EPA /NRC CONCLUDE NO REGULATIONS OR TECHNICAL SPECIFICATIONS VIOLATED.
FOLLOWUP:
VIA 0F LETTER, NRC IS REQUESTING LICENSEE T0:
9 1.
REVISE MAXIMUM LOWER LIMIT OF DETECTION (LLD) SPECIFIED IN TECHNICAL SPECIFICATIONS.
2.
PREVENT EXPOSURE TO GENERAL PUBLIC FROM EXISTING CONTAMINATION 3.
ESTliBLISH COMPREHENSIVE ENVIRONMENTAL MONITORING PROGRAM.
POTENTIAL GENERIC ISSUES BEING FOLLOWED BY NRR-PM 1.
REVIEW COMPATIBILITY OF TECHNICAL SPECIFICATION AT OTHER NUCLEAR POWER PLANTS SURVEILLANCE LLD TO 10 CFR APPENDIX I CRITERIA.
2.
iiE'/IEW POTENTIAL FOR ANNUAL RELEASES AT OTHER NUCLEAR POWER PLANTS IN ACCORDANCE WITH APPENDIX I TO EVENTUALLY EXCEED 40 C:R 190.
I REGION V REVIEWING RANCHO SECO LIQUID RELEASES IN 1985.
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REACTOR SCRAM SUMMAFY T
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1 WEEK ENDING 04/06/S6 I.' PLANT SPECIFIC DATA R'
'DATE-SITE'
~UNITfPOWER RPS CAUSE' COMPLI-'
YTD CATIONS ' TOTAL-
'04/02/06[ SUMMER 1-
.100 A~
-EQUIP /TORB-GEN NO 3
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-04/02/06'-BRUNSWICK
.1
-64 A EQUIP /DC-ELEC NO 2
04/03/86 FORT ST. VRAIN' 1
24 M-EQUIP /ELEC.
YES
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1-1A EQUIP / MODE SWCH NO 3
-04/04/86 FITZPATRICK' 1
88 A
. EQUIP /TURB VLV' NO
-1 04/05/86 OUAD CITIES 1
3A' EQUIP /FD BP VLV NO
.1-04/06/86-BRUNSWICK:
1 1A EDLIP/FD CNTL NO 3-p
SUMMARY
OF COMPLICATIONS-SITE-UNIT COMPLICATIONS:
,y FORT-ST. IVRAIN 1 LOSS OF AC/ LOSS'OF C'IRCULATION/ NOBLE GAS RELEASE-
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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES p
f.
SCRAMS FOR WEEK ENDING p
04/06/06 L.
SCRAM CAUSE POWER NUMBER NUMBER 1985 l-OF NORMALIZED (6)
WEEKLY SCRAMS (5)
TO 1985 AVERAGE (3)(4)
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- POWER'>15%
EQUIP. RELATED
>15%
4 4.0 5.4 (68%)
PERS. RELATED(7) >15%
.O O.0 2.0 (25%)
OTHER(8)'
.>15%
0 0.0 0.6 (17%)
- Subtotal **
4 4.0
-8.0.
- POWER <15%.
EQUIP. RELATED
<15%
3 3.0-1.3 (54%)
.PERS. RELATED-
<15%
0 0.0 0.9'(38%)
OTHER
<25%
0 0.0 0.2 ( 8%)
- Subtotal **
3 3.0 2.4
- Total ***
L 7
7.0 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER NUMBER 1985 OF NORMALIZED WEEKLY SCRAMS TO 1985 AVERAGE MANUAL SCRAMS 1
1.0 3.0 AUTOMATIC SCRAMS 6
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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 0F PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
2.
RECOVERY COMPLICATED 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 & DIVIDING BY 52 WEEKS / YEAR 4.
IN 1985, THERE WERE AN ESTIMATED TOTAL 0F 541 AUTOMATIC a MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES).
THIS YIELDS 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 PEACTORS 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.
ENCLOSURE 3 Pagt No, 1
..- 04/08/E6 OPERATING REACTORS EVENTS MEETING FOLLOWUP ITE15 AS OF MEETINS 86-11 CN APRIL 7,1986 (IN ASCEND!NS MEETINS DATE, NSSS VENDOR, FACILITY ORtER)
MEETINS FACILITY FESPONSIBLE TASK DESCRIPil0N SCHEDULE CLOSED CATE C0VEPTS NUM!ER/
NSSS VEN20R/
DIVISIONI COMPLET.
BY DOCUMENT, MEETINS EVENTDESCRIP.
INDIVIDUAL DATE(S)
MEETINS, ETC.
IATE B5-13 TURKEY FOINT 3 PSB /MILH0AN J.
FEVIEW AIEGUACY CF B3VERNDR 04/22/26 0 FEN
/ /
05/13/85 W / FOST-TRIP
/
IESIGN CN TUSP!NE DRIVEN AFh 01/05/86 LOSS OF AFW FUMPS 10/13/B5 26-03 AEKANSAS I IE / JORDAN E IIENTIFY WHAT IS CTUAL LESISN 04/20/86 OPEN
/ /
01/27/96 EW / CESIGN
/
IN B1b FluiS 03/31/Bo o!
IEFICIENCY IN
/ /
EMER6ENCY FEEEWATER SYSTEM E6-03 MCEUIFE CHFS/IIEM AN D FEVIEW NDVEPEER 1, 19E5 McEUIRE 04/30/96 0 FEN
/ /
01/27/86 W / START 4F i
ELENT MD LETERMINE It FAILUFE
/ /
WITHCESRAED TO REPAIR VALVE MOTOR OPERATOR
/ /
HPSI SYSTEM PRICR TO STAD.T-LP WAS IN VIOLATION OF TECH SPECS PEGUIPEMENT E6-06 W PLANTS IE /JORCAN E REVIEW FEFORTABILITY OF ITEMS 04/20/86 CFEN
/ /
03/03/26 W / SINGLE
/
SUCH AS $1NSLE FAILUPE OF P-10 03/31/56 FAILUEE OF INTERLCCF
/ /
NUCLEAR INSTRUMENTATION INTERLOCK P-10 B6-10 SAN DNSFRE 2 IE /JCREAN E REVIEW ADEGUACY OF REFORTING OF 05/01/E6 CFEN
/ /
03/31/E6 CE / COMMON M0tE
/
THIS EVENT
/ /
FAILURE OF BOTH
/ /
SH'JTICWN C00 LINS TRAINS 66-10 SAN ONCFFE 2 iE /JCSDH E E DLUATE NEED FOR IE NOTICE 05/01/86 0 FEN
/ /
03/31/26 CE / C0 2 04 MODE
/
/ /
FAILURE OF EDTH
/ /
SHUTLCWN C0OLING TRAINS 86-10 OYSTER CREEK kFR /MIRASLIA F CHECK CN TM1 FOR USE OF SIMILAR 05/01/86 0 FEN
/ /
03/31/26 SE / LEVEL
/
SWITCHES
/ /
! WITCH SETF0!NT
/ /
DRIFT E6-10 OYSTER CREEK NRR / HOUSTON W RESQLVE THE QUESTION 0F THE 06/30/86 0 FEN
/ /
03/31/26 EE / LEVEL
/
ACCEPTABILITY OF BLIND 0 WITCHES
/ /
SWITCH SETPOINT AND DELET10N OF CAILY CHANNEL
/ /
DRIFT CHECK
y r.
{Page Not I2 f.04/08/86 i
OPERATIN6 REACTORS EVENTS MEETING FDLLONUP ITEMS AS OF MEETING 86-11 ON APRIL 7,1986 (IN ASCENDING MEETINE DATE, NSSS VENDOR, FACILITY ORDER)
MEETING' FACILITY?
RESPONSIBLE TASK DESCRIPi!CN SCHEDULE-CLOSED DATE COMMENTS NUNDER/ : : NSSS VENDOR /.
DIVISION /.
COMPLET. BT DOCUMENT,.
- MEETING. EVENT DESCRIP.
INDIVIDUAL
'DATE(S)
MEETIN6,ETC.
DATE h
86-10
- BRAIDWOOD 1.
NRR /ROSSI E REWEST REFDRT OF EVENT FEDM 05/01/86 CPEN
//
03/31/E6 W / WATER
/
LICENSEE
/ /
-HAMMER IN MAIN
//
STEAM LINE 96-10
//
LO3/31/56. W../ WATER
/
/ /
HARMER IN MAIN.
/ /
. STEAM LINE 86-10 PACCAM NECK NPR /SPE15 i ASSESS TFE FOTENTIAL FOR C5/30/96 OPEN
/-/
03/31/96 W / NEW SMALL
- /
SENERIC J FLICABILITY
/ /
BREAKLOCA
//
RESULTS 86-10 HADftAM NECK NRR /RDSSI E ASSURE THAT THE COUECTIVE 05/01/86 0 FEN
//
03/31/86 W / NEW SMALL
/
ACT!0NS AEE ACEQUATE FRIOR 10
/
I' BREAK LOCA RESTART
/ /
RESULTS D