U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/05/96 - 03/06/96 ** EVENT NUMBERS ** 30062 30063 30064 30065 30066 30067 30068 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 03/05/96 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 04:17 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 03:00[EST]| |NRC NOTIFIED BY: CROSSMAN |LAST UPDATE DATE: 03/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |COLLINS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE AND FEDERAL AGENCIES REGARDING A 45-GALLON OIL | | SPILL INTO INTAKE BAY | | | | THE LICENSEE NOTIFIED THE VIRGINIA STATE WATER QUALITY BOARD, THE VIRGINIA | | DEPARTMENT OF EMERGENCY SERVICES, AND THE U.S. COAST GUARD REGARDING THE | | SPILL OF APPROXIMATELY 45 GALLONS OF LUBRICATING OIL INTO THE CIRCULATING | | WATER INTAKE BAY WHICH IS LOCATED ON LAKE ANNA. THE OIL LEAKED FROM THE OIL | | COOLER FOR THE 1-CW-P-1B CIRCULATING WATER PUMP. | | | | THE LICENSEE'S OIL RESPONSE TEAM IS CURRENTLY REMOVING THE OIL FROM THE | | INTAKE BAY. THE 1-CW-P-1B CIRCULATING WATER PUMP HAS BEEN TAGGED OUT OF | | SERVICE, AND ITS OIL RESERVOIR HAS BEEN DRAINED. THE NRC RESIDENT INSPECTOR | | WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/05/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 07:09 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 06:06[EST]| |NRC NOTIFIED BY: MANSELL |LAST UPDATE DATE: 03/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOERFLEIN 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 +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR TRIP FROM 100% DUE TO GENERATOR LOCKOUT | | | | WITH THE UNIT OPERATING AT 100% POWER, AN AUTOMATIC TURBINE TRIP/REACTOR | | TRIP OCCURRED DUE TO A GENERATOR LOCKOUT. THE CAUSE OF THE LOCKOUT IS | | UNKNOWN, AND IS CURRENTLY BEING INVESTIGATED. ALL CONTROL RODS INSERTED | | FOLLOWING THE REACTOR TRIP. THE ROD BOTTOM LIGHT FOR CONTROL ASSEMBLY J-13 | | FAILED TO ILLUMINATE FOLLOWING THE TRIP, BUT THE LICENSEE INDEPENDENTLY | | VERIFIED THAT THE CONTROL ELEMENT HAD INSERTED PROPERLY. | | | | FOLLOWING THE REACTOR TRIP, THE #23 MOTOR-DRIVEN AUXILIARY FEEDWATER (AFW) | | PUMP FAILED TO START AS EXPECTED. OPERATORS MANUALLY OPENED THE INJECTION | | VALVES FROM THE TURBINE-DRIVEN AFW PUMP (WHICH HAD AUTOMATICALLY STARTED | | DUE TO LOW-LOW STEAM GENERATOR LEVEL) TO THE #23 AND #24 STEAM GENERATORS. | | DECAY HEAT IS BEING REMOVED VIA THE STEAM DUMPS TO THE MAIN CONDENSER. ALL | | OTHER SYSTEMS FUNCTIONED AS EXPECTED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30064 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/05/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 11:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 09:48[CST]| |NRC NOTIFIED BY: TERRENCE DORAZIO |LAST UPDATE DATE: 03/05/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 91 POWER OPERATION | 91 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 ENTRY DUE TO AN INADEQUATE TAG-OUT WORK SCOPE | | DURING MAINTENANCE ON A SAFETY INJECTION SYSTEM FLOW ORIFICE | | | | WHILE PERFORMING SCHEDULED MAINTENANCE ON THE '2B' SAFETY INJECTION PUMP, | | IT WAS DISCOVERED THAT THE WORK SCOPE INCLUDED DISASSEMBLY AND CLEANING OF | | A FLOW ORIFICE (2-SI-07MB). THE BOLTS WERE LOOSENED WITH A CATCH CONTAINER | | UNDERNEATH FOR DRAINING. THE WORK ON THIS ORIFICE WAS STARTED ON THE | | AFTERNOON SHIFT ON MARCH 4, 1996, AND THE UNIT ENTERED A LIMITING CONDITION | | FOR OPERATION FOR THE 'B' TRAIN OF SAFETY INJECTION BEING OUT OF SERVICE. | | | | AT 0948 CST, ON MARCH 5, 1996, AN ERROR WAS DISCOVERED. APPARENTLY, THE | | OUT-OF-SERVICE TAG-OUT BOUNDARY OR WORK SCOPE WAS INADEQUATE IN THAT IT DID | | NOT INCLUDE FLOW ORIFICE 2-SI-07MB, AND THE FLOW ORIFICE WAS NOT ISOLATED | | FROM THE '2A' SAFETY INJECTION PUMP DISCHARGE. AT 0959 CST, THE CROSS-TIE | | VALVE FROM THE '2A' TO '2B' SAFETY INJECTION PUMP (VALVE 2-SI-8821B) WAS | | CLOSED, AND THIS ACTION ISOLATED THE FLOW ORIFICE FROM THE 2A SAFETY | | INJECTION PUMP DISCHARGE. TECHNICAL SPECIFICATION 3.0.3 WAS ENTERED AT | | 0948 CST, AND IT WAS EXITED AT 1000 CST WHEN THE ORIFICE WAS NO LONGER IN | | CONJUNCTION WITH THE DISCHARGE OF THE '2A' SAFETY INJECTION PUMP. | | | | THE LICENSEE HAS STOPPED ALL WORK AND IS CURRENTLY RE-EVALUATING THE WORK | | SCOPE IN ITS ENTIRETY TO ENSURE THAT THERE ARE NO MORE PROBLEMS. THE | | LIMITING CONDITION FOR OPERATION FOR THE 'B' TRAIN OF SAFETY INJECTION | | BEING OUT OF SERVICE IS STILL IN EFFECT. ALL OTHER EMERGENCY CORE COOLING | | SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE OPERABLE AT THIS TIME. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30065 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 03/05/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 12:02 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 10:15[CST]| |NRC NOTIFIED BY: CAROL KRONICH |LAST UPDATE DATE: 03/05/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 30 POWER OPERATION | 30 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY SIRENS INOPERABLE | | | | THE LICENSEE WAS NOTIFIED AT 1045 (CST) THAT THE EMERGENCY SIRENS IN SCOTT | | COUNTY WERE INOPERABLE SINCE 1015 (CST). THE VENDOR (FULTON TECHNOLOGY) IS | | WORKING ON RESTORING THE SIRENS AND EXPECTS THEM TO BE RESTORED WITHIN ONE | | HOUR. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/05/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 13:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 13:05[EST]| |NRC NOTIFIED BY: RICH DONOVAN |LAST UPDATE DATE: 03/05/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AC FUSES USED IN DC CIRCUITS IN THE EMERGENCY POWER SUPPLIES | | | | DURING IMPLEMENTATION OF A FUSE CONTROL PROGRAM, THE LICENSEE DISCOVERED | | THAT AC FUSES WERE BEING USED IN PLACE OF DC FUSES IN CERTAIN CIRCUITS. AC | | FUSES WERE FOUND IN THE DC CONTROL CIRCUITS FOR THE GAS TURBINE AND ALSO IN | | LOAD CENTERS WHICH SUPPORT THE EMERGENCY DIESEL GENERATOR. THE EXACT | | NUMBER OF FUSES INVOLVED WAS NOT KNOWN, BUT THEY WERE ALL RATED AT 10 AMPS | | AND BELOW. | | | | THE LICENSEE DID NOT KNOW WHY THE WRONG FUSES WERE INSTALLED BUT IS | | INVESTIGATING THE PROBLEM. OTHER AREAS OF THE PLANT ARE ALSO BEING | | INSPECTED TO SEE IF ANY OTHER SYSTEMS ARE AFFECTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/05/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 15:00 [ET]| |RX TYPE: [3] CE |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 13:55[CST]| |NRC NOTIFIED BY: PIPKINS |LAST UPDATE DATE: 03/05/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM (SPDS) DEGRADED | | | | SPDS DISPLAY POINTS (19 OF 37) WILL BE TEMPORARILY DEGRADED OVER THE NEXT 3 | | WEEKS. THE SPDS POINTS WILL BE DISCONNECTED AND INOPERABLE DURING THE | | PERFORMANCE OF CORRECTIVE MAINTENANCE THAT IS NECESSARY TO CORRECT A | | PROBLEM THAT HAS RESULTED IN FOUR RECENT FAILURES. THE PLANNED MAINTENANCE | | WILL AFFECT ABOUT ONE THIRD OF THE SPDS SCREEN LAYOUT. THE 19 DIGITAL | | INPUTS TO SPDS AFFECT ESFAS STATUS INDICATIONS. ALSO, 22 OF THE POINTS | | AFFECTED WILL BE INFORMATION THAT WOULD BE INPUTTED TO THE SEQUENCE OF | | EVENTS (SOE) SYSTEM THUS IMPACTING POST TRIP ASSESSMENT CAPABILITY. THE 19 | | SPDS POINTS ARE ALSO SOE POINTS. THE SPDS AND SOE POINTS ARE NOT SAFETY | | RELATED. THE PLANT MONITORING COMPUTER IS CONSIDERED NOT AVAILABLE DURING | | AND AFTER AN ACCIDENT. IT IS ESTIMATED THAT THE SPDS POINTS WILL BE OUT OF | | SERVICE FROM 3/5 TO 3/22. THE SPDS POINTS INVOLVED ARE DIGITAL POINTS THAT | | ARE DUPLICATIONS OF CONTROL ROOM ANNUNCIATOR POINTS THAT ARE PROVIDED AS AN | | INDICATION TO THE CONTROL ROOM OPERATORS THAT A PLANT PROTECTION SYSTEM OR | | EMERGENCY SAFEGUARDS SYSTEM ACTUATION HAS OCCURRED OR THAT A SAFETY BUS | | UNDERVOLTAGE OR GROUND CONDITION EXISTS. THE ANNUNCIATOR WILL REMAIN | | OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30068 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/05/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 19:20 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 03/05/96 | +------------------------------------------------+EVENT TIME: 16:06[CST]| |NRC NOTIFIED BY: B. HANSON |LAST UPDATE DATE: 03/05/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM INOPERABLE | | | | THE HPCI SYSTEM WAS DECLARED INOPERABLE TO PERFORM CORRECTIVE MAINTENANCE. | | THE LICENSEE HAD TO ISOLATE THE STEAM SUPPLY TO HPCI TO REPAIR A LEAKING | | DRAIN VALVE. THE PLANT IS IN A 7-DAY LIMITING CONDITION FOR OPERATION IN | | ACCORDANCE WITH TECHNICAL SPECIFICATION 3.5.C.2. OTHER CORE COOLING | | SYSTEMS ARE OPERABLE. THE LICENSEE INTENDS TO MAKE REPAIRS AND EXPECTS THE | | HPCI SYSTEM TO BE REPAIRED WITHIN 24 HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+