U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/22/97 - 07/23/97 ** EVENT NUMBERS ** 32658 32663 32664 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32658 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 07/21/97 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 09:55 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 07/21/97 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: PAUL BRANDT |LAST UPDATE DATE: 07/22/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 Y 73 POWER OPERATION | 73 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY NOTIFICATION SIRENS INOPERABLE | | | | AT 0900, THE LICENSEE DISCOVERED THAT ALL EMERGENCY SIRENS WERE INOPERABLE | | AS A RESULT OF THE INOPERABILITY OF THE MASTER TRANSMITTER. THE LICENSEE | | ACTIVATED THE BACKUP TRANSMITTER, AND THE SIRENS WERE RESTORED AT 0915. THE | | LICENSEE REPORTED THAT THE SIRENS HAD LAST BEEN TESTED ON 7/18/97. THE NRC | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE 0947 7/22/97 FROM BRANDT TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. AFTER FURTHER REVIEW OF THE | | EVENT, THE LICENSEE HAS DETERMINED THAT THE EMERGENCY SIRENS WOULD HAVE | | BEEN CAPABLE OF ACTIVATING. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY | | THE LICENSEE. NOTIFIED R2DO (POTTER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32663 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 07/22/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 13:21 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 07/22/97 | +------------------------------------------------+EVENT TIME: 12:42[EDT]| |NRC NOTIFIED BY: HANKE |LAST UPDATE DATE: 07/22/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |BOB DENNIG (NRR) EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |RICH BARRETT (MGR) IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR MANUALLY TRIPPED AFTER SEVERAL RODS DROPPED INTO THE CORE. | | | | THE REACTOR WAS MANUALLY TRIPPED FROM 100% POWER AFTER MULTIPLE CONTROL | | RODS DROPPED INTO THE CORE. ALL RODS FULLY INSERTED INTO THE CORE. ALL | | THREE TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS AUTOMATICALLY STARTED ON | | LOW-LOW STEAM GENERATOR WATER LEVEL. STEAM GENERATOR WATER LEVELS ARE BEING | | MAINTAINED WITHIN THEIR NORMAL RANGE. THE TRAIN 1 STEAM GENERATOR "C" | | AUXILIARY FEEDWATER FLOW CONTROL VALVE, CV-3-2818, STUCK OPEN AND THE | | LICENSEE IS ISOLATING THE VALVE. THE LICENSEE MANUALLY SHUT THEIR MAIN | | STEAM LINE ISOLATION VALVES TO CONTROL REACTOR COOLANT SYSTEM TEMPERATURE. | | REACTOR COOLANT TEMPERATURE IS BEING MAINTAINED AT A Tave NO LOAD CONDITION | | OF 547øF USING THE STEAM GENERATOR ATMOSPHERIC VALVES (THERE ARE NO LEAKING | | STEAM GENERATOR TUBES). ALL EMERGENCY CORE COOLING SYSTEMS AND THE | | EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF NEEDED (THE ELECTRICAL | | GRID IS STABLE). | | | | THE LICENSEE IS INVESTIGATING WHY THE CONTROL RODS DROPPED INTO THE CORE | | AND WHY AUXILIARY FEEDWATER CONTROL VALVE, CV-3-2818, STUCK OPEN. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | *** UPDATE @ 1421 EDT ON 07/22/97 BY HANKE TAKEN BY MACKINNON *** | | | | THE THREE TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS HAVE BEEN SECURED AND | | NORMAL FEEDWATER HAS BEEN RETURNED TO SERVICE TO MAINTAIN PROPER STEAM | | GENERATOR WATER LEVELS. THE LICENSEE IS PRESENTLY INVESTIGATING A POWER | | SUPPLY PROBLEM WHICH CAUSED THE "1AC" POWER CABINET (CONTROL ROD CABINET) | | TO DEENERGIZE. NO PRIMARY OR SECONDARY CODE SAFETY VALVES OPENED. R2DO | | (POTTER) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS INFORMATION BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32664 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 07/23/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 00:23 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/22/97 | +------------------------------------------------+EVENT TIME: 20:30[CDT]| |NRC NOTIFIED BY: VERNON CARLSON |LAST UPDATE DATE: 07/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRIP OF HPCS PUMP BREAKER DURING IN-SERVICE TESTING FOR REASONS UNKNOWN. | | | | "WHEN ATTEMPTING TO START THE HIGH PRESSURE CORE SPRAY (HPCS) PUMP TO | | SUPPORT IN-SERVICE TESTING, THE PUMP BREAKER TRIPPED. INDICATIONS AT THE | | BREAKER WAS THE TRIP WAS CAUSED BY THE 'A' PHASE INVERSE TIME OVERCURRENT | | RELAY. INVESTIGATIONS ARE ONGOING TO DETERMINE IF IT IS A RELAY OR PUMP | | MOTOR PROBLEM." | | | | THE LICENSEE HAD ENTERED THE 14 DAY TECH SPEC LCO A/S 3.5.1 ACTION B AT | | 0200CDT ON 7/22/97 FOR PLANNED MAINTENANCE ON THE SAFETY-RELATED UNIT ROOM | | COOLER. AT THAT TIME ALL OTHER ECCS EQUIPMENT WAS VERIFIED OPERABLE. | | OPERATORS DID NOT OBSERVE ANY UNUSUAL AMPERAGE INDICATION WHILE MONITORING | | IN-RUSH CURRENT PRIOR TO THE BREAKER TRIP. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+