ML20215C996
| ML20215C996 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Fermi, Point Beach, Byron, Pilgrim, Cook, 05000000 |
| Issue date: | 12/11/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| OREM-86-041, OREM-86-41, NUDOCS 8612160146 | |
| Download: ML20215C996 (16) | |
Text
,
0EC 11 1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON NOVEMBER 24, 1986 - MEETING 86-41 On November 24, 1986, an Operating Reactor Events meeting (86-41) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on November 17, 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. provides a sumary of those presented events that will be input to NRC's performance indicator program as significant events.
AS/
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION
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4 DEC 11586 Harold R. Denton cc:
R. Vollmer D. Hood l
J. Taylor B. J. Youngblood C. Heltames T. Colburn R. Starostecki G. Lear D. Ross D. Wigginton T. Murley, Reg. I J. Stefano J. Nelson Grace, Reg. II R. Jolliffe' J. Keppler, Reg. III R. Auluck R. D. Martin, Reg. IV J. Zwolinski J. B. Martin, Reg. V E. Adensam W. Kane Reg. I L. Olshan S. Ebneter, Reg. I V. Noonan R. Walker, Reg. II C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield E. Rossi G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. Arlotto
DEC 111986 ENCLOSURE 1 LIST OF ATTENDEES f
OPERATING REACTORS EVENTS BRIEFING (86-41)
NOVEMBER 24. 1986 NAME DIVISION NAME DIVISION G. Holahan NRR/0 RAS M. Virgilio NRR/0 RAS W. Swenson NRR/0 RAS R. Jolliffee IE/EAB L. Olshan NRR/DPL-A D. Basdekas RES/RAB S. Aggarwal RES/ DES M. Chiramal AE00 D. Brinkman IE/DI S. Israel AE00 V. Benaroya NRR/PAF0 M. Caruso NRR/ORAS G. Cwalina NRR/DHFT J. Clifford NRR D. Allison IE C. Ader OCM/TMR W. Regan NRR/PWR-A D. Vassallo NRR/ DBL B. Clayton NRR/DPL-A G. Murphy ORNL/N0AC Y. Togo AEOD H. Bailey IE/DEPER R. Woodruff IE/DEPER D. Hood NRR/PWR-A J. Stone IE/VPB E. Adensam NRR/ DBL F. Brenneman NRR/0 RAS R. Vollmer NRR E. Jordan IE K. Kniel NRR/DSR0 R. Baer IE/DEPER E. Rossi NRR/PWR-A F. Schroeder NRR/PWR-B D. Tondi NRR/0 RAS R. Houston NRR/ DBL B. Sheron DSR0/NRR J. Rosenthal IE/EAB
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-41 NOVEMBER 24, 1986 SIGNIFICANT EVENTS POINT BEACH 1 SCRAM WITH COMPLICATIONS l
i COOK 1 SCRAM WITH COMPLICATIONS BYRON 2 LOSS OF BOTH COMPONENT COOLING WATER PUMPS PILGRIM LOSS OF 0FFSITE POWER OTHER EVENTS OF INTEREST MCGUIRE 2 SCRAM WITH COMPLICATIONS FERMI 2 LARGE WATER SPILL FROM CONDENSATE STORAGE TANK
POINT BEACH I - SCRAM WITH COMPLICATIONS NOVEMBER 17, 1986 (T. COLBURN, NRR)
PROBLEM:
LOSS OF RED INSTRUMENT BUS SIGNALED 1 OUT OF 2 LOGIC FOR FEED FLOW / STEAM FLOW MISMATCH RESULTING IN REACTOR TRIP COMPLICATED BY EQUIPMENT MALFUNCTIONS CAUSE:
SHORTED DIODE IN INVERTER SUPPLYING RED INSTRUMENT BUS CAUSES 4 BLOWN FUSES AND LOSS OF BUS SIGNIFICANCE 1 BRIEF LOSS OF ONE OF THREE AUXILIARY FEEDWATER SOURCES (0NE MOTOR-DRIVEN AFW PUMP DISCHARGE VALVE IS POWERED FROM RED INSTRUMENT BUS)
ONE SOURCE RANGE NUCLEAR INSTRUMENT DETECTOR FAILED LOW ONE INTERMEDIATE RANGE (IR) DETECTOR APPARENTLY FAILED LOW DISCUSSION:
REACTOR SCRAMMED FROM 100 PERCENT POWER ON CONCURRENT LOW S/G LEVEL AND FEED FLOW / STEAM FLOW MISMATCH SIGNAL GENERATED BY INSTRUMENT BUS FAILURE POWER RESTORED TO INSTRUMENT BUS VIA ALTERNATE INVERTER IN 4 MINUTES ANY LOSS OF AN INSTRUMENT BUS WILL RESULT IN A REACTOR TRIP (4 FEED FLOW / STEAM FLOW MISMATCH CHANNELS, 2 PER LOOP, 1 0F 2 LOGIC, EACH POWERED FROM SEPARATE INSTRUMENT BUS)
LOSS OF RED OR BLUE INSTRUMENT BUS ALSO CAUSES LOSS OF POWER TO A OR B MOTOR-DRIVEN A !i PUMP DISCHARGE VALVE, TURBINE-DRIVEN AFW PUMP UNAFFECTED SUBSEQUENT CHECKS OF FAILED IR DETECTOR INDICATED INCORRECT COMPENSATING V0LTAGE SET FOR LOW POWER, NOT A DETECTOR FAILURE FOLLOWUP:
RESIDENT INSPECTOR FOLLOWING LICENSEE ACTIONS
COOK 1 - SCRAM WITH COMPLICATIONS NOVEMBER 22, 1986 (D. WIGGINTON, NRR)
PROBLEM:
TURBINE TRIP AND SUBSEQUENT REACTOR TRIP
- SOURCE RANGE INSTRUMENT CHANNEL FAILED TO ENERGIZE
- SEQUENCE OF EVENTS MONITOR FAILED TO RECORD "B" REACTOR TRIP BREAKER OPEN
- STEAM FLOW METER FAILED HIGH CAUSE:
EQUIPMENT MALFUNCTIONS SIGNIFICANCE:
REACTOR TRIP WITH EQUIPMENT MALFUNCTIONS OPERATING WITH BATTERY GROUNDED DISCUSSION:
THRUST BEARING MONITOR WAS KNOWN TO BE MISPOSITIONED:
UNTRIED PLANT PROCEDURE IN PLACE TO BYPASS TRIP IF REPOSITIONING BECAME NECESSARY TURBINE CONTROL VALVE TESTING EXCEEDED EXPECTED PERTURBATION ON SYSTEM AND INITIATED TRIP SOURCE RANGE INSTRUMENTATION KNOWN NOT TO AUTOMATICALLY ENERGIZE:
WESTINGHOUSE GENERIC PROBLEM.
PLANT MOD IN PREPARATION TO ELIMINATE PROBLEM REACTOR TRIP BREAKER "B" OPENED BUT DID NOT RECORD ON SEQUENCE OF EVENTS MONITOR.
VERIFIED OPENED STEAM FLOW TRANSMITTER ON LOOP 4 FOUND TO BE FAILED AND WAS REPLACED FOLLOWUP:
SEQUENCE OF EVENTS MONITOR AND BATTERY GROUND UNDER INVESTGATION BY LICENSEE
- REPORTED BATTERY GROUND IS NOT EXPECTED TO BE A CONTRIBUTOR TO EVENT
BYRON 2 - LOSS OF BOTH COMPONENT COOLING WATER (CCW)6 PUMPS NOVEMBER 20, 1986 (L. OLSHAN, NRR) i PROBLEM:
LOSS OF COMPONENT WATER SYSTEM CAUSE:
EQUIPMENT MALFUNCTION, OPEN RELIEF VALVE DOWNSTREAM OF EXCESS LETDOWN HEAT EXCHANGE 4
SIGNIFICANCE:
NO POST-LOCA SIGNIFICANCE BECAUSE NON-ESSENTIAL LINE ISOLATES ON SI SIGNAL CCW HAS SINGLE FAILURE VULNERABILITY REQUIRING OPERATOR RESPONSE WHEN EXCESS LETDOWN HEAT EXCHANGERS ARE IN SERVICE DISCUSSION:
PLANT SHUTDOWN, INITIAL FUEL LOAD COMPLETE SLAVE RELAY TEST OF EXCESS LETDOWN HEAT EXCHANGER ISOLATION CIRCUITS IN PROGRESS.
VALVE OPEN WITH ONE CCW PUMP OPERATING AND ONE CCW PUMP IN STANDBY.
PRESSURE SURGE CAUSES RELIEF VALVE TO LIFT SURGE TANK DRAINS, RUNNING CCW PUMP TRIPS ON LOW SURGE TANK LEVEL STANDBY CCW PUMP AUTO STARTS ON LOW DISCHARGE PRESSURE RELIEF VALVE STILL OPEN, OTHER SIDE OF SURGE TANK DRAINS STANDBY CCW PUMP TRIPS ON LOW SURGE TANK LEVEL OPERATORS MANUALLY ISOLATED FLOW PATH TO EXCESS LET DOWN HEAT EXCHANGER AND RESTORED LEVEL IN SURGE TANK WITHIN ABOUT 12 MINUTES.
F0LLOWUP:
i REGION AND LICENSEE TO DETERMINE WHY RELIEF VALVE DID NOT RESEAT PLANT PROCEDURES BEING CHANGED TO PROHIBIT CHANGING CCW FLOW STATUS WHEN EXCESS LETDOWN VALVE IS OPEN TO AVOID SYSTEM PRESSURE PERTURBATIONS IE NOTICE UNDER CONSIDERATION
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PILGRIM - LOSS OF 0FFSITE POWER f.
NOVEMBER 19, 1986 (J. ROSENTHAL, IE)
PROBLEM:
LOSS OF ALL THREE OFFSITE POWER LINES DURING SNOW STORM CAUSE:
COMBINATION OF HIGH WINDS, SNOW, AND SALT SPRAY BUILD-UP SIGNIFICANCE:
COMPLETE LOSS OF 0FFSITE POWER; SHUTDOWN COOLING ISOLATED CIRCUMSTANCES:
SITE LOCATED ON CAPE C0D BAY PLANT HAS BEEN SHUT DOWN SINCE APRIL (RCS TEMP 114*F)
HEAVY WET SNOWFALL OF ABOUT 4 INCHES WITH WINDS OF 45 TO 50 MPH WITH GUSTS TO 60 MPH 20,000 GALLONS OF DIESEL FUEL AVAILABLE, ADEQUATE FOR MORE THAN 100 HOURS DISCUSSION:
OFFSITE POWER LOST AT ABOUT 0805 BOTH DIESEL GENERATORS START AND LOAD SHUTDOWN COOLING ISOLATED ON LOSS OF POWER OPEN TELEPHONE LINK ESTABLISHED BETWEEN HQ, REGION AND SITE SHUTDOWN COOLING RESTORED AT ABOUT 0920 345 KV LINE FROM NORTH RESTORED TO YARD BUT NOT PLANT AT 1103 SAFETY BUSES REMAINED ON DIESEL GENERATORS UNTIL LOAD DISPATCHER TROUBLESH00TS YARD OFFSITE POWER RESTORED TO PLANT AT ABOUT 1130 DIESEL GENERATORS PARALLELED TO GRID PRIOR TO SHUTDOWN EDGs SHUTDOWN AT 1238 FOLLOWUP:
LIKELIHOOD OF RECURRENCE WARRANTS ATTENTION
OTHER EVENT OF INTEREST MCGUIRE 2 - SCRAM WITH COMPLICATIONS NOVEMBER 20, 1986 (D. HOOD, NRR)
PROBLEM:
AN ENGINEER DISCONNECTED FUSES FROM CIRCUIT BY OPENING A DRAWER DURING SYSTEM WALKDOWN THIS RESULTED IN LOSS OF NON-VITAL BUS AND A REACTOR TRIP COMPLICATED BY EQUIPMENT MALFUNCTIONS CAUSE:
PERSONNEL ERROR EQUIPMENT MALFUNCTION SIGNIFICANCE:
REACTOR TRIP COMPLICATED BY SMALL STEAM LEAK AND DEGRADED NEUTRON MONITORING SYSTEM (SOURCE RANGE AND INTERMEDIATE)
DISCUSSION:
11/20/86, PLANT EMPLOYEE WAS PLANNING WORK ON MODIFICATIONS TO TERMINATE CABLES IN 6900 VOLT SWITCH GEAR ROOM.
EMPLOYEE OPENED A DRAWER AND THUS DISCONNECTED CIRCUIT RESULTING IN LOSS OF NON-VITAL BUS.
THIS CAUSED A REACTOR COOLANT PUMP TRIP AND REACTOR TRIP FROM 100% POWER MOTOR-DRIVEN AFW PUMPS WERE STARTED BY OPERATORS PRIOR TO AUTO-START SIGNAL.
TURBINE-DRIVEN PUMP STARTED AUTOMATICALLY.
A NON-SAFETY FEEDWATER HIGH PRESSURE RELIEF VALVE LIFTED AND RESEATED A COUPLER (FLEXIBLE METALLIC HOSE DOWNSTREAM 0F FEEDWATER HEATER RELIEF VALVE) FAILED CAUSING A STEAM LEAK IN TURBINE BUILDING INTERMEDIATE RANGE MONITOR DID NOT FUNCTION PROPERLY BECAUSE IT WAS UNDER-COMPENSATED, AS A RESULT, SOURCE MONITOR HAD TO BE MANUALLY ENERGIZED FOLLOWUP:
LICENSEE IS INVESTIGATING EVENT NRR AND REGION II FOLLOWING UP
OTHER EVENT OF INTEREST FERMI 2-LARGEWATERSPILLFROMCONDENSATESTORAGE! TANK NOVEMBER 17, 1986 (R. J0LLIFFE, IE)
PROBLEM:
283,000 GAL OF WATER LEAKED FROM THE CONDENSATE STORAGE l
TANK (CST)
CAUSE:
PERSONNEL ERROR (IMPROPER VALVE LINEUP)
SIGNIFICANCE:
DEGRADATION OF EQUIPMENT IMPORTANT TO SAFETY LARGE UNCONTROLLED WATER SPILL DISCUSSION:
PLANT IN COLD SHUTDOWN FOR MAINTENANCE OUTAGE CONTROL R0D DRIVE (CRD) PUMP MINIFLOW VALVE WAS OPENED FOLLOWING MAINTENANCE ACTIVITIES CST ISOLATION VALVE WAS INADVERTENTLY LEFT CLOSED TEST RETURN LINE WAS OVERPRESSURIZED VIA CRD PUMP SECTION OF TEST RETURN LINE MOVED UPWARD TEST RETURN LINE WELDED CONNECTION TO BOTTOM 0F CST FAILED 100,000 GAL PUMPED FROM CST TO RAD WASTE SYSTEM IN ATTEMPT TO PREVENT ENTIRE CST CONTENTS FROM SPILLING THIS RESULTED IN A (VERY LOW ACTIVITY LEVEL) RADI0 ACTIVE WATER / RESIN SPILL IN RADWASTE AREA (INSIDE THE PLANT) 283,000 GAL FROM CST LEAKED INTO DIKED AREA SURROUNDING TANK DIKE WATER SAMPLED 8 CONTAINED NO RADIATION DIKE WATER SEEPED INTO THE GROUND NO RADIATION RELEASE OFFSITE FOLLOWUP:
SENIOR RESIDENT INSPECTOR /NRC RESTART TEAM / REGION 3 - WILL FOLLOW LICENSEE ACTIONS
FERMI 2 - LARGE 11ATER SPILL FR0f! CST 4
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MOBV - liOTOR OPERATED BUTTERFLY VALVE i
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REACTOR SCRAM SUttfARY WEEK ENDING 11/23/86 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW
. TOTAL 15%
15%
11/17/86 POINT BEACH 1
100 A EQUIP / INVERTER YES 2
0 2
11/18/86 LACROSSE 1
96 A EQUIP / RELAY NO 6
10 16/
11/19/86 PALO VERDE 1
100 A EQUIP /FD CNTL NO 13 0
13 11/20/86 MCGUIRE 2
100 A PERSONNEL YES 5
2 7
11/20/86 CATAWBA 2
100 A EQUIP /MFW SYSTM NO 4
2 6
11/20/86 WNP 2
15 A EQUIP /MFW CNTL N('-
4 3
7 11/22/86 COOK 1
90 A EQUIP / ELECT YES 4
1 5
11/22/86 CATAWBA 2
25 A.
EQUIP /MFW CNTRL NO 5
2 7
11/23/96 BYRON 2
0M EQUIP /RPI NO O
1 1
SUMMARY
OF COMPLICATIONS SITE UNIT COMPLICATIONS POINT BEACH 1 TEMPORARY LOSS OF ONE AFW SOURCE ONE SRM AND ONE IRM FAILED LOW i
MCGUIRE 2 STEAM LEAK IN TURBINE BUILDING l
COOK 1 SRM FAILED TO ENERGIZE i
STEAM FLOW METER FAILED i
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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES t
SCRAMS FOR WEEK ENDING 11/23/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)
AVERAGE l AVERAGE YTD (3)(4)
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POWER >15%
- c.,.
EQUIP. RELATED
>15%
6 4.5 5.4 (68%)
PERS.'RELATED(6) >15%
1 1.9 2.0 (25%)
OTHER(7)
>15%
0 0.5 0.6 ( 7%)
- Subtotal **
7 6.9 8.0
- POWER <15%
EQUIP. RELATED
<15%
2 -
1.4 1.3 (54%)
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PERS. RELATED
<15%
0 0.8 0.9 (38%)
OTHER
<15%
0 0.2 0.2 ( 8%)
- Subtotal **
2 2.4 2.4
- Total ***
9 9.3 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY -
SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1
1.0 1.0 AUTOMATIC SCRAMS 8
8.2 9.4
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NOTES 1.' ' PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGil 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 PROCEDURE.
2.
RECOVERY C0t1 PLICATED BY EQUIPHENT 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 AND DIVIDING BY 52 WEEKS / YEAR.
~ ~
4.
IN 1985. THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
~
5.
BASED ON 100 REACTORS HOLDING A FULL POWER LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.
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EflCLOSURE 3 Fage No.
1 S!6NIFICANT EVENTS FREGUENCY PERFORMANCE INDICATOR No. 3 PLANT NAME EVENT EVENT DESCRIPTION SIGNIFICANCE QTR DATE I
BYs0N 2 11/20/B6 LOSS OF BOTH COMPONENT C00LIN6 WATER PUMPS POTENTIAL FOR OR ACTUAL DE6RADATION OF 1
(CCWP).ONE CCWP MANUAL SHUTDOWN DURING TEST SAFETY-RELATED EQUIPMENT CAUSES REL!EF VALVE DOWNSTREAM OF EXCESS LETDOWN HEAT EICHAN6ER TO OPEN. VALVE DOES NOT RESEAT.0THER Pufto TRIPS ON LOW SURSE TANK LEVEL COOK I 11/22/B6 TURBINE TRIP RESULTED IN REACTOR TRIP WHILE SCRAM WITH COMPLICATIONS 1
TESTING TURB!NE CONTROL VALVE. COMPLICATIONS INCLUDE GROUND ON MAIN BATTERY, TURBINE THRUST BEARIN6 FAILURE S16NAL, STEAM FLOW METER FAILURE, AND SOURCE RANGE MONITOR FAILED TO ENER611E.
PIL6 RIM 11/19/06 LOSS OF ALL THREE OFFSITE PCWER LINES DURINS LOSS OF 0FFSITE PCWER 1
SNOW STORM. SHUTDOWN COOLING RESTORED IN AFPROIIMATELY ONE HOUR AND FIFTEEN MINUTES POINT BEACH I 11/17/86 INVERTER FAILURE CAUSED LDSS OF RED BUS, STEAM SCRAM WITH COMPLICAT10NS 1
FLOW! FEED FLOW MISMATCH AND REACTOR TRIP. SOURCE RANGE MONITOR FAILED LOW AND INTERMEDIATE RANGE MONITOR WAS NOT PROPERLY COMPENSATED.
MOTOR-0 RIVEN AFW PUMP O!SCHARBE VALVE CONTROLLER TEMPORARILY LOST.
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