U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/05/96 - 12/06/96 ** EVENT NUMBERS ** 31409 31410 31411 31412 31413 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31409 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/05/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 11:45 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/05/96 | +------------------------------------------------+EVENT TIME: 08:51[EST]| |NRC NOTIFIED BY: CARL RICH |LAST UPDATE DATE: 12/05/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -CIRCUIT BREAKER TO CONTAINMENT LEAK DETECTOR VALVES INADVERTENTLY OPENED- | | | | WHILE PERFORMING MAINTENANCE ACTIVITIES ON THE 'A' CONTROL ENCLOSURE | | CHILLER, A MAINTENANCE TECHNICIAN INADVERTENTLY OPENED A CIRCUIT BREAKER | | TO CONTAINMENT LEAK DETECTOR VALVES #SV-26-190A & C WHICH CAUSED THESE | | VALVES TO FAIL CLOSED DUE TO THE LOSS OF ELECTRICAL POWER. THE TECHNICIAN | | THEN CLOSED THE BREAKER AND THE VALVES RETURNED TO THEIR NORMAL FULL OPEN | | POSITION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31410 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 12/05/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 16:57 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/05/96 | +------------------------------------------------+EVENT TIME: 13:08[CST]| |NRC NOTIFIED BY: BRUCE SCHOENBACK |LAST UPDATE DATE: 12/05/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 15 STARTUP | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TURBINE TRIP, MAIN FW ISOLATION, & AUX FW ACTUATION DURING PLANT STARTUP- | | | | DURING MAIN TURBINE GENERATOR SYNCHRONIZATION AND POWER ESCALATION, | | STEAM GENERATOR 'B' WATER LEVEL INCREASED TO THE HIGH-HIGH LEVEL SETPOINT. | | THIS CAUSED THE MAIN TURBINE TO TRIP, THE MAIN FEEDWATER SYSTEM TO ISOLATE, | | AND THE AUXILIARY FEEDWATER SYSTEM TO ACTUATE, AS DESIGNED. CONTROL ROOM | | OPERATORS INSERTED CONTROL RODS TO REDUCE POWER FROM 15% TO 2% POWER. | | | | THE PLANT IS STABLE IN MODE 2 (STARTUP) AT 2% POWER. THE LICENSEE PLANS TO | | INCREASE POWER LATER TODAY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31411 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/05/96 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/05/96 | +------------------------------------------------+EVENT TIME: 16:02[CST]| |NRC NOTIFIED BY: STEVE FLANDERS |LAST UPDATE DATE: 12/05/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - INCORRECT VALVE CLOSED DURING RHR PUMP TECH SPEC SURVEILLANCE TEST - | | | | DURING THE PERFORMANCE OF A TECH SPEC SURVEILLANCE TEST OF THE RHR PUMP, | | CONTROL ROOM OPERATORS WERE SHUTTING DOWN #21 COMPONENT COOLING WATER (CCW) | | PUMP. THE OPERATOR CLOSED #21 CCW HEAT EXCHANGER CROSS CONNECT VALVE | | #MV-32122 INSTEAD OF #21 CCW INLET VALVE #MV-32160. MV-32160 IS NORMALLY | | CLOSED FOLLOWING #21 CCW PUMP SHUTDOWN. | | | | THE EFFECT OF CLOSING MV-32122 WAS TO ISOLATE CCW TO 'A' TRAIN SAFEGUARDS | | EQUIPMENT. THIS CAUSED A LOW PRESSURE SIGNAL IN THE CCW SYSTEM WHICH | | AUTOMATICALLY STARTED #21 CCW PUMP. | | | | THE OPERATOR IMMEDIATELY REOPENED MV-32122 RESTORING CCW TO 'A' TRAIN | | SAFEGUARDS EQUIPMENT. THE OPERATOR THEN SHUT #21 CCW PUMP DOWN IN THE | | NORMAL MANNER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31412 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 12/05/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 21:45 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/05/96 | +------------------------------------------------+EVENT TIME: 20:47[EST]| |NRC NOTIFIED BY: JOE WALDMAN |LAST UPDATE DATE: 12/05/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOHN HANNON EO | | |FRANK CONGEL AEOD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 88 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TS REQD PLANT S/D DUE TO BOTH SETS OF MANUAL Rx TRIP PUSH BUTTONS INOP - | | | | MAINE YANKEE HAS A TOTAL OF FOUR SAFETY RELATED DC POWER TRAINS. THE PLANT | | DESIGN BASIS REQUIRES CABLE SEPARATION IN EACH SAFETY RELATED DC POWER | | TRAIN. | | | | DURING A PLANT REVIEW PER NRC GENERIC LETTER 96-01, THE LICENSEE DISCOVERED | | THAT TWO SAFETY RELATED DC CABLES IN THE 'C' SAFETY RELATED DC CABLE TRAY | | ARE POWERED FROM THE 'D' TRAIN SAFETY RELATED DC POWER SOURCE AND TWO | | SAFETY RELATED DC CABLES IN THE 'D' SAFETY RELATED DC CABLE TRAY ARE | | POWERED FROM THE 'C' TRAIN SAFETY RELATED DC POWER SOURCE. | | | | THUS, THE LICENSEE DECLARED 2 OF 2 SETS OF MANUAL REACTOR TRIP PUSH BUTTONS | | INOPERABLE EVEN THOUGH THEY ARE FUNCTIONAL. | | | | TECH SPEC 3.9 REQUIRES THAT AT LEAST 1 OF 2 SETS OF MANUAL REACTOR TRIP | | PUSH BUTTONS BE OPERABLE. THE LICENSEE ENTERED TECH SPEC 3.0.A WHICH | | REQUIRES THE LICENSEE TO COMPLY WITH TECH SPEC 3.9 WITHIN ONE HOUR OR TO | | PLACE THE PLANT IN AT LEAST HOT SHUTDOWN MODE WITHIN THE FOLLOWING 6 HOURS. | | | | AT 2047, THE LICENSEE BEGAN SHUTTING THE PLANT DOWN TO MAKE REPAIRS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, WILL NOTIFY MAINE STATE | | OFFICIALS, AND PLANS TO ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31413 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 12/06/96 | |UNIT: [ ] [2] [ ] STATE: TN |NOTIFICATION TIME: 02:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/06/96 | +------------------------------------------------+EVENT TIME: 00:33[EST]| |NRC NOTIFIED BY: MICHAEL MUNROE |LAST UPDATE DATE: 12/06/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES HOSEY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP - LOSS OF TWO REACTOR COOLANT PUMPS (RCPs) | | | | "AT 0033 EDT, 12/6/96, UNIT 2 REACTOR TRIPPED AUTOMATICALLY FROM FULL POWER | | AS A RESULT OF LOSS OF POWER TO THE UNIT 2 6.9 KV UNIT BOARDS, RESULTING IN | | LOSS OF LOOP 1 AND 3 RCPs. THE REACTOR FIRST OUT ALARM WAS "RCP BUS 3 | | UNDER VOLTAGE CHANNEL III". | | | | "THE CAUSE FOR THE LOSS OF POWER TO THE 2A 6.9 KV START BUS, WHICH FEEDS | | THE 2A & 2C 6.9 KV UNIT BOARDS, HAS NOT BEEN DETERMINED AT THIS TIME. THE | | TRIP TEAM IS BEING ASSEMBLED TO INITIATE THE TRIP INVESTIGATION. | | | | "DUE TO LOSS OF POWER TO THE 2B 6.9 KV SHUTDOWN BOARD ALL FOUR EDGs | | STARTED, THE 2B D/G TIED ONTO THE 2B SHUTDOWN BOARD AND IS PRESENTLY | | CARRYING THAT LOAD. AS A RESULT OF THE BLACKOUT SIGNAL THE STANDBY 2B-B | | CENTRIFUGAL CHARGING PUMP, THERMAL BARRIER BOOSTER PUMP AND 2B COMPONENT | | COOLING WATER (PUMP) STARTED. ALSO, AS A RESULT OF THE REACTOR TRIP | | SIGNAL, ALL THREE AUX FEEDWATER PUMPS STARTED. | | | | "ALL SYSTEMS AND COMPONENTS OPERATED AS EXPECTED FOR THIS EVENT. THE RCS | | TEMPERATURE WENT TO 536øF FOLLOWING THE TRIP & THE RCS WAS BORATED IN | | ACCORDANCE WITH EMERGENCY PROCEDURES. UNIT 2 IS BEING MAINTAINED IN MODE 3 | | WITH RCS TEMPERATURE @ 547øF AND RCS TEMPERATURE AT 2235 PSIG." | | | | ALL RODS FULLY INSERTED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER AS | | NECESSARY TO REMOVE DECAY HEAT. THE 2B EDG WILL CONTINUE TO SUPPLY IT'S | | SHUTDOWN BUS WHILE THE PROBLEM WITH THE START BUS IS INVESTIGATED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+