U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/02/95 - 01/03/95 ** EVENT NUMBERS ** 28201 28202 28203 28204 28205 28206 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28201 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 01/02/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 03:03 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 01/01/95 | +------------------------------------------------+EVENT TIME: 23:30[EST]| |NRC NOTIFIED BY: B. LEWIS |LAST UPDATE DATE: 01/02/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 +------------------------------------------------------------------------------+ | REACTOR BUILDING/TORUS VACUUM BREAKER ISOLATION VALVE OPENED WHEN POWER TO | | THE ISOLATION VALVE WAS LOST. | | | | REACTOR BUILDING/TORUS VACUUM BREAKER ISOLATION VALVE (AO5040B) WAS FOUND | | DEENERGIZED (VALVE OPEN) DURING NIGHTLY ROUNDS (THE REACTOR BUILDING/TORUS | | VACUUM BREAKER REMAINED CLOSED). DURING CONTROL ROOM NIGHTLY ROUNDs OF THE | | BACK PANELS IN CONTROL ROOM THE INDICATING LIGHT FOR REACTOR BUILDING/TORUS | | VACUUM BREAKER ISOLATION VALVE WAS DEENERGIZED. DEENERGIZATION OF THIS | | LIGHT MEANS THAT ELECTRICAL POWER TO THE ISOLATION VALVE HAS BEEN LOST | | CAUSING THE VALVE TO AUTOMATICALLY OPEN. LOGS ARE TAKEN ONCE PER SHIFT AND | | THE POWER INDICATING LIGHT FOR "AO5040B" WAS ENERGIZED DURING MID SHIFT | | CHECK (1500 - 2300 ET). AN INVESTIGATION FOUND THAT THE FUSE HOLDER FOR | | ISOLATION VALVE (AO5040B) WAS LOOSE CAUSING A LOSS OF POWER TO THE | | ISOLATION VALVE. THE FUSE HOLDER WAS TIGHTENED RESULTING IN ELECTRICAL | | CONTINUITY BEING RESTORED TO THE ISOLATION VALVE. LICENSEE SAID THAT NO | | MAINTENANCE OR TESTING HAD TAKEN PLACE ON THE ISOLATION VALVE. LICENSEE | | WILL NOTIFY STATE OF THIS EVENT ON 01/03/95. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/02/95 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 16:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/02/95 | +------------------------------------------------+EVENT TIME: 10:10[PST]| |NRC NOTIFIED BY: GARY ANDERSON |LAST UPDATE DATE: 01/02/95 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE AND LOCAL AGENCIES OF CHEMICAL SPILL ON-SITE. | | | | APPROXIMATELY 125 GALLONS OF ACTIBROM (BIO-DISPERSANT) WAS SPILLED DURING | | PRODUCT OFFLOAD. THIS WAS DETERMINED TO BE A REPORTABLE QUANTITY (>10 LBS) | | AND REPORTED TO BOTH STATE AND LOCAL AGENCIES PER PROCEDURE. 50 GALLONS WAS | | RELEASED INTO THE OCEAN AS A RESULT OF THE SPILL WHILE THE REMAINING 75 | | GALLONS IS CONTAINED AND WILL BE CLEANED UP. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28203 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 01/02/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 21:17 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/02/95 | +------------------------------------------------+EVENT TIME: 18:33[EST]| |NRC NOTIFIED BY: EDWARD EVANS |LAST UPDATE DATE: 01/02/95 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 63 POWER OPERATION | 63 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED A REACTOR ENCLOSURE ISOLATION DUE TO A FUSE FAILURE ON A | | RADIATION MONITOR DURING A SURVEILLANCE TEST. | | | | "ON JANUARY 2, 1995, AT 1833 HRS A UNIT 2 REACTOR ENCLOSURE ISOLATION | | OCCURRED WHEN A FUSE BLEW IN THE NSSSS LOGIC. THE FUSE BLEW WHEN AN I&C | | TECHNICIAN SWITCHED the "2A" REACTOR ENCLOSURE VENTILATION RADIATION | | MONITOR TO OPERATE DURING A SURVEILLANCE TEST. THE FOLLOWING ADDITIONAL | | ISOLATIONS OCCURRED DUE TO THE ISOLATION SIGNAL: | | - UNIT 2 INSTRUMENT GAS | | - UNIT 1/UNIT 2 CAC VALVES | | - UNIT 1/UNIT 2 NITROGEN MAKEUP VALVES | | | | "AT 1910 HRS THE FUSE WAS REPLACED AND SUBSEQUENTLY ALL SYSTEMS WERE | | RETURNED TO NORMAL. I&C IS CURRENTLY INVESTIGATING THE EVENT. THE ISOLATION | | WAS ONLY ON THE "A" LOGIC. THE "A" STANDBY GAS FAN DID NOT DRAW DOWN THE | | REACTOR BUILDING. THIS WAS EXPECTED SINCE THE "A" FAN WAS BEING USED TO | | INERT UNIT 1 CONTAINMENT (HAD INSTRUMENT INSTALLED FOR THIS PURPOSE WHICH | | LIMITED FLOW). THE "B" CHANNEL DID NOT ACTUATE SINCE IT WAS NOT UNDER | | TEST." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28204 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/03/95 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 03:13 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/03/95 | +------------------------------------------------+EVENT TIME: 02:30[EST]| |NRC NOTIFIED BY: SLATTERY |LAST UPDATE DATE: 01/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED FEDERAL AGENCY THAT THEIR SPILLWAY EMERGENCY DIESEL | | FAILED TO START DURING ITS PERFORMANCE TEST. | | | | WHILE PERFORMING O-PT-1 (PERFORMANCE TEST) SPILLWAY EMERGENCY DIESEL | | (1-EE-EG-04) FAILED TO START. EMERGENCY DIESEL IS USED AS AN EMERGENCY | | BACKUP POWER SYSTEM FOR LAKE ANNA DAM SPILLWAY GATE (CONTROL LAKE LEVEL) | | AND DAM CONTROL CENTER. LICENSEE IMMEDIATELY NOTIFIED THE FEDERAL EMERGENCY | | RESPONSE CENTER (FERC) AS REQUIRED BY THEIR LICENSE, VPAP-2802 | | (ADMINISTRATIVE PROCEDURE USED FOR REPORTABILITY DETERMINATION). LICENSEE | | IS MAKING THIS EVENT NOTIFICATION BECAUSE THEY NOTIFIED ANOTHER FEDERAL | | AGENCY. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28205 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/03/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 03:44 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/03/95 | +------------------------------------------------+EVENT TIME: 02:30[CST]| |NRC NOTIFIED BY: J REED |LAST UPDATE DATE: 01/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 3 STARTUP | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE ENTERED TECH SPEC REQUIRED SHUTDOWN PROCEDURE AND MANUALLY | | SCRAMMED THE UNIT AFTER RCIC WAS DECLARED INOPERABLE. | | | | STARTUP WAS IN PROGRESS (EXITING 85 DAY MAINTENANCE OUTAGE) WITH REACTOR | | VESSEL PRESSURE AT 253psig AND 1.75 BYPASS VALVES OPEN WHEN LICENSEE | | ENTERED TECH SPEC 4.5.E @ 1442 CT 01/02/95 (12 HOUR PERIOD TO COMPLETE RCIC | | TESTING FOLLOWING MAINTENANCE). DURING QCOS1300-1 (PERIODIC RCIC | | OPERABILITY TEST) RCIC STEAM INLET GOVERNOR VALVE WOULD NOT RESPOND TO | | SIGNALS FROM ITS FLOW CONTROLLER. AT 2124 CT 01/02/95 LICENSEE DECLARED | | RCIC INOPERABLE AND TECH SPEC 3.5.E.4 (ORDERLY SHUTDOWN TO BE INITIATED & | | REACTOR VESSEL PRESSURE BE REDUCED BELOW 150 psig WITHIN 24 HOURS) WAS | | ENTERED. LICENSEE ENTERED THEIR NORMAL SHUTDOWN PROCEDURE (QCGP2-3) AND AT | | 0230 CT LICENSEE INITIATED A MANUAL REACTOR SCRAM. ALL RODS FULLY INSERTED | | INTO THE CORE. LICENSEE IS COOLING DOWN THE PLANT USING THEIR RWCU BLOWDOWN | | VALVES (LOW DECAY HEAT) AND IF NECESSARY THEIR MAIN CONDENSER IS AVAILABLE | | IF IT NEEDS TO BE USED TO COOLDOWN THE PLANT. | | LICENSEE IS INVESTIGATING THE ROOT CAUSE OF WHY RCIC STEAM GOVERNOR VALVE | | WOULD NOT RESPOND TO SIGNALS FROM ITS FLOW CONTROLLER. LICENSEE THINKS THE | | PROBLEM WITH RCIC GOVERNOR VALVE NOT RECEIVING ITS SIGNAL FROM THE FLOW | | CONTROLLER IS A PROBLEM WITH ITS CONTROL SIGNAL MODIFIER WHICH IS LOCATED | | IN A BOX LOCATED BETWEEN THE FLOW CONTROLLER AND THE HYDRAULICS WHICH | | CONTROL THE GOVERNOR VALVE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28206 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 01/03/95 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 05:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/03/95 | +------------------------------------------------+EVENT TIME: 04:21[EST]| |NRC NOTIFIED BY: BILL HARRIS |LAST UPDATE DATE: 01/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |STEVEN VIAS/LESSER RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP |ELINOR ADENSAM EO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CARR FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LATCHES (TWO LATCHES ONE IN UPPER RIGHT HAND SIDE OF THE CUBICLE AND THE | | OTHER LATCH IN THE UPPER LEFT HAND SIDE OF THE CUBICLE) WHICH HOLDS BREAKER | | IN ITS COMPARTMENT FOUND TO BE UNLATCHED. | | | | WHILE PERFORMING CONTROL BOARD WALKDOWN FOR UNIT 2 THE ONCOMING SENIOR | | REACTOR OPERATOR (SRO) DISCOVERED THAT 2-FCV-63-8, A SAFETY RELATED VALVE | | (USED TO SUPPLY SUCTION FROM CONTAINMENT SUMP TO HIGH & INTERMEDIATE HEAD | | SAFETY INJECTION PUMPS AFTER REFUELING WATER STORAGE TANK LEVEL GETS LOW), | | HAD NO INDICATION OF VALVE POSITION. THE UNIT OPERATOR REPLACED THE LIGHT | | BULB AND THE 480V BREAKER WAS VERIFIED CLOSED, BUT THERE WAS STILL NO | | INDICATION OF THE VALVE POSITION. A SRO WAS DISPATCHED TO THE BREAKER. THE | | SRO VERIFIED THE FUSES WERE GOOD. WHILE CHECKING THE FUSES THE BREAKER IN | | ITS COMPARTMENT BEGAN TO MOVE AND THE SRO NOTICED THE LOCAL INDICATING | | LIGHT FOR THE BREAKER FLICKERED. THE SRO PUSHED THE BREAKER SNUGLY INTO ITS | | COMPARTMENT UNTIL IT WAS FULLY LATCHED AND VERIFIED BREAKER HAD PROPER | | INDICATION. THE VALVE, INDICATED CLOSED AT THE BREAKER COMPARTMENT AND | | REMOTELY IN THE MAIN CONTROL ROOM. IT WAS SUBSEQUENTLY DETERMINED THAT THIS | | VALVE WOULD NOT HAVE OPERATED AND THE ACTIONS OF LCO 3.5.2 WAS ENTERED AND | | EXITED DUE TO "A" TRAIN OF ECCS BEING INOPERABLE. A COMPLETE CONTROL BOARD | | WALKDOWN WAS PERFORMED AND NO OTHER SAFETY RELATED VALVES WERE FOUND | | WITHOUT POSITION INDICATION. FURTHER INVESTIGATION OF WHY THE BREAKER WAS | | NOT FULLY ENGAGED REVEALED THE "COMPARTMENT RETENTION LATCH - TWO FOR EACH | | BREAKER" WAS NOT FULLY ENGAGED. THE SHIFT OPERATING SUPERVISOR DIRECTED ALL | | 480V MOLDED CASE BREAKERS TO BE CHECKED FOR SIMILAR CONDITION. NUMEROUS | | BREAKERS WERE FOUND TO BE IN AN UNLATCHED OR PARTIALLY UNLATCHED (ONE OF | | THE TWO LATCHES UNLATCHED) CONDITION, AND THESE BREAKERS WERE CORRECTED ON | | THE SPOT DUE TO THE POTENTIAL FOR THESE BREAKERS TO BE IN AN UNLATCHED | | CONDITION AND BECOME DISENGAGED, AND THE POSSIBILITY OF BOTH TRAINS OF THE | | ESF EQUIPMENT TO BE INOPERABLE AT THE SAME TIME. LICENSEE DETERMINED THAT | | THEY WERE IN AN UNANALYZED CONDITION. LICENSING AND NUCLEAR ENGINEERING | | WERE CONSULTED OF THIS CONDITION. LICENSEE SAID THAT THEY STILL CHECKING | | BREAKERS AT THIS TIME FOR UNIT 1 AND UNIT 2. | | | | ****UPDATE 0538EST 01/03/95 BY BILL HARRIS TAKEN BY MACKINNON**** | | | | LICENSEE UPGRADED THIS EVENT TO AN UNUSUAL EVENT CLASSIFICATION PER THEIR | | RADIOLOGICAL EMERGENCY PLANS "HU15" (CONDITIONS THAT WARRANT INCREASED | | AWARENESS OF PLANT OPERATING STAFF). LICENSEE CONSIDERS THIS A SEISMIC | | CONCERN TO THE PLANT IN THAT IF THEY HAD A SEISMIC EVENT AND THE BREAKERS | | WERE UNLATCHED THE BREAKERS COULD POSSIBLY DISENGAGE FROM THEIR POWER | | SOURCE AND BECOME INOPERABLE. LICENSEE WILL NOTIFY STATE AND LOCAL | | OFFICIALS OF THIS EVENT CLASSIFICATION. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+