U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/03/95 - 01/04/95 ** EVENT NUMBERS ** 28204 28205 28206 28207 +----------------------------------+ +-----------------------+ |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: |STEVEN VIAS 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 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 | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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. | | | | * * * * UPDATE 1002 EST 1/3/95 BY DENNIS DIMOPHULOS TAKEN BY WEAVER * * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 0959 EST. A COMPLETE WALKDOWN OF THE | | SAFETY RELATED BOARDS AND NON SAFETY RELATED BOARDS IN SEISMIC AREAS WAS | | COMPLETED. ALL DISCREPANCIES WERE CORRECTED ON THE SPOT, WITH THE | | EXCEPTION OF ONE CASE WHERE ONE OF THE TWO LATCHES WAS BROKEN. THE CAUSE | | OF THIS CONDITION IS UNDER INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO INFORMED THE RDO | | (VIAS); EO (DENNIG); FEMA (SHULL) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28207 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/03/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 10:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/03/95 | +------------------------------------------------+EVENT TIME: 10:43[EST]| |NRC NOTIFIED BY: CROKE |LAST UPDATE DATE: 01/03/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS 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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAVE A PROBLEM WITH THEIR DIRECT NUCLEAR | | ALERT SYSTEM. | | | | THEY DETERMINED THIS WHILE TESTING THEIR DIRECT COMMUNICATIONS SYSTEM TO | | THE STATES OF VERMONT, MASSACHUSETTS AND NEW HAMPSHIRE. WHEN THEY REQUESTED | | THE STATES TO CALL BACK NO RING BACK WAS RECEIVED. THEY SUSPECT THE RINGER | | ON THE PHONE, SINCE THE STATE OF NEW HAMPSHIRE WAS ON THE PHONE WHEN THE | | LICENSEE PICKED IT UP EVEN THOUGH IT DID NOT RING WHEN THE CALL BACK WAS | | MADE. THE TELEPHONE COMPANY IS AWARE OF THE PROBLEM. THE RESIDENT INSPECTOR | | AND STATE WILL BE INFORMED. | | | +------------------------------------------------------------------------------+