U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/30/95 - 05/31/95 ** EVENT NUMBERS ** 28866 28867 28868 28869 28870 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28866 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 05/30/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:20 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: SLIWA / RASPLEY |LAST UPDATE DATE: 05/31/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ED GOODWIN EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |WRIGHT FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 16 POWER OPERATION | 16 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UE DUE TO TS REQUIRED PLANT SHUTDOWN DUE TO UNIDENTIFIED LEAK > TS LIMIT- | | | | LICENSEE HAS MEASURED A 2.9 GPM UNIDENTIFIED WATER LEAK RATE INCREASE IN | | THE DRYWELL OVER A 24-HOUR PERIOD. | | | | TECH SPEC LCO A/S 3.6.D.1.b REQUIRES THE LICENSEE TO REDUCE THE | | UNIDENTIFIED LEAK RATE TO LESS THAN A TWO GPM INCREASE IN A 24-HOUR PERIOD | | WITHIN FOUR HOURS OR PLACE THE PLANT IN AT LEAST HOT SHUTDOWN CONDITION | | WITHIN THE NEXT 12 HOURS AND COLD SHUTDOWN CONDITION WITHIN THE FOLLOWING | | 24 HOURS. | | | | LICENSEE BEGAN SHUTTING THE PLANT DOWN FROM 100% POWER AND WAS AT 16% POWER | | AND DECREASING AT THE TIME OF THE CALL TO THE NRC OPERATIONS CENTER. | | | | AT 1200, LICENSEE DECLARED AN UNUSUAL EVENT DUE TO A TECH SPEC REQUIRED | | PLANT SHUTDOWN. | | | | LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR | | OF THE DECLARATION OF THE UNUSUAL EVENT. | | | | **** UPDATE FROM SULLIVAN RECEIVED BY TROCINE AT 03:03 ON MAY 31, 1995 **** | | | | THE UNIT ENTERED COLD SHUTDOWN AT 02:47, AND THE UNUSUAL EVENT WAS | | TERMINATED AT 02:50 ON MAY 31, 1995. THE LICENSEE IDENTIFIED A PACKING | | LEAK ON A 3/4-INCH MANUAL VALVE OFF OF THE 'B' RECIRCULATION SUCTION VALVE. | | (THIS MANUAL VALVE IS USED FOR CHEMICAL DECONNING.) THE ESTIMATED RESTART | | DATE IS JUNE 1, 1995. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR, STATE AND LOCAL GOVERNMENTS, | | AND THE MEDIA. THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (SHANBAKY), NRR | | EO (ADENSAM), AND FEMA (SHULL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28867 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/30/95 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 15:48 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 14:03[EDT]| |NRC NOTIFIED BY: JOHN MANLY |LAST UPDATE DATE: 05/30/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 | M/R Y 18 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL Rx SCRAM DUE TO HIGH MAIN TURBINE VIBRATION DURING PLANT STARTUP - | | | | DURING THE RECENT UNIT 2 REFUELING OUTAGE (OUTAGE #4), 3 OF 3 LOW PRESSURE | | ROTORS OF THE GENERAL ELECTRIC MAIN TURBINE WERE REPLACED. | | | | DURING THE STARTUP OF UNIT 2 FOLLOWING REFUELING OUTAGE #4, WITH THE | | REACTOR AT 18% POWER, LICENSEE WAS STARTING UP THE MAIN TURBINE. GENERAL | | ELECTRIC COMPANY REPRESENTATIVES WERE PRESENT TO OBSERVE THE STARTUP. | | WHEN THE MAIN TURBINE REACHED 1550 RPM (RATED SPEED IS 1800 RPM), | | THE VIBRATION OF BEARING #6, LOCATED BETWEEN THE FIRST AND SECOND LOW | | PRESSURE STAGES, EXCEEDED THE SELF-IMPOSED ADMINISTRATIVE LIMIT OF 14 MILS. | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE MAIN TURBINE. AS THE MAIN | | TURBINE BEGAN TO COAST DOWN IN SPEED, THE VIBRATION OF BEARING #6 CONTINUED | | TO INCREASE. THE VIBRATION MAY HAVE INCREASED TO AS MUCH AS 50 MILS. | | | | CONTROL ROOM OPERATORS MANUALLY SCRAMMED THE REACTOR FROM 18% POWER SO | | THAT THE MAIN CONDENSER VACUUM COULD BE BROKEN IN ORDER TO EXPEDITE THE | | SLOW DOWN OF THE MAIN TURBINE. ALL CONTROL RODS INSERTED COMPLETELY, AND | | ALL SYSTEMS FUNCTIONED AS EXPECTED. THE MAIN STEAM ISOLATION VALVES | | CLOSED AUTOMATICALLY, AS EXPECTED, ON A LOW MAIN CONDENSER VACUUM SIGNAL. | | STEAM IS BEING USED BY NORMAL STATION STEAM LOADS. | | | | UNIT 2 IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE HIGH MAIN TURBINE VIBRATION. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28868 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 05/30/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:12 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 13:35[EDT]| |NRC NOTIFIED BY: MIKE BOURASSA |LAST UPDATE DATE: 05/30/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 125-VOLT DC STATION BATTERY SYSTEM VOLTAGE DEGRADED FOR 20 MINUTES - | | | | WHILE TESTING AN EMERGENCY LIGHTING TRANSFORMER CIRCUIT BREAKER, LICENSEE | | TECHNICIANS RACKED OUT THE BREAKER. THIS UNEXPECTEDLY CAUSED THE 125-VOLT | | DC STATION BATTERY SYSTEM VOLTAGE TO DEGRADE TO 122 VOLTS DC. TECH SPEC | | REQUIRED MINIMUM SYSTEM VOLTAGE IS 125 VOLTS DC. | | | | AT 1335, THE CONTROL ROOM RECEIVED A 125-VOLT DC SYSTEM TROUBLE ALARM. | | | | AT 1355, THE TECHNICIANS RACKED THE BREAKER BACK IN, AND THE SYSTEM TROUBLE | | ALARM CLEARED WITH THE SYSTEM VOLTAGE INDICATED AT 126 VOLTS DC. | | | | THE SYSTEM IS PRESENTLY OPERATING AT AN INDICATED VOLTAGE OF 132 VOLTS DC. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE SYSTEM VOLTAGE DROP WHEN THE | | BREAKER IS RACKED OUT. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28869 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/30/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 22:16 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 21:55[EDT]| |NRC NOTIFIED BY: MARVIN JOHNSON |LAST UPDATE DATE: 05/31/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOUGLAS COLLINS RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | -LESS THAN 15% OF UNIT 1 CONTROL ROOM ANNUNCIATORS LOST FOR UNKNOWN REASONS | | | | UNIT 1 LOST LESS THAN 15% OF THE CONTROL ROOM ANNUNCIATOR CAPABILITY FOR | | UNKNOWN REASONS. LOST ARE THE ANNUNCIATORS FOR THE STANDBY (REMOTE) | | SHUTDOWN FACILITY, THE FIRE PROTECTION PANELS, THE INSTRUMENT AIR | | COMPRESSORS, THE HVAC BOARDS, AND THE OPERATOR AID COMPUTER PANEL. | | | | PLANT PERSONNEL ARE MONITORING LOCAL PANELS AND OPERATING EQUIPMENT LOCALLY | | UNTIL THE PROBLEM IS CORRECTED. | | | | INSTRUMENT AND CONTROL TECHNICIANS ARE INVESTIGATING THE CAUSE AND | | DETERMINING CORRECTIVE ACTIONS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | **UPDATE DATE\TIME: 5/31/95 @ 0415 EDT *FROM LICENSEE: SMALL BY:McGINTY** | | THE LICENSEE REPLACED A BAD ANNUNCIATOR CARD THAT FED THE "1-AD-13, A-2 AND | | A-3" ANNUNCIATORS. THE CARD WAS CAUSING THE FUSES TO BLOW THAT FEED THE | | POWER SUPPLY FOR THOSE CABINETS. THE ANNUNCIATORS ARE NOW WORKING | | CORRECTLY AND THE WORK ORDER HAS BEEN CLOSED OUT. THE LICENSEE WILL INFORM | | THE RESIDENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28870 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 05/31/95 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 04:34 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 22:45[MST]| |NRC NOTIFIED BY: ROBERSON |LAST UPDATE DATE: 05/31/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 65 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 65% DUE TO CLOSURE OF A FEEDWATER ISOLATION VALVE DURING | | THE REPLACEMENT OF A COIL IN THE SOLENOID. | | | | UNIT 1 WAS AT 65% POWER AFTER RECENTLY COMPLETING A REFUELING OUTAGE. AT | | APPROXIMATELY 2242 MST, AN AUTOMATIC REACTOR TRIP OCCURRED ON LOW STEAM | | GENERATOR LEVEL FOR SG NO. 2. PRIOR TO THE REACTOR TRIP, REPLACEMENT OF A | | COIL IN THE "D" SOLENOID OF FEEDWATER ISOLATION VALVE (FWIV) "137" WAS IN | | PROGRESS, WHEN FWIV "137" UNEXPECTEDLY CLOSED. CLOSURE OF THE FWIV CAUSED | | A LOSS OF MAIN FEEDWATER FLOW TO SG NO. 2. | | | | THE EVENT WAS CLASSIFIED AS AN UNCOMPLICATED REACTOR TRIP. THE CAUSE OF | | THE CLOSURE OF THE FWIV IS UNDER INVESTIGATION. ALL CONTROL RODS FULLY | | INSERTED INTO THE CORE, AND THE PLANT IS STABLE AT NOP/NOT. THE PLANT IS | | STEAMING AS REQUIRED TO THE MAIN CONDENSER, AND AUXILIARY FEEDWATER PUMP | | "N" IS FEEDING BOTH SG's. THERE WERE NO PROBLEMS WITH TRANSFERS OF | | ELECTRICAL BUSES, AND ALL ECCS's AND EDG's ARE OPERATIONAL. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR AND THE STATE. | +------------------------------------------------------------------------------+