U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/18/94 - 10/19/94 ** EVENT NUMBERS ** 27916 27917 27918 27919 27920 27921 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27916 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 10/18/94 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 11:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/18/94 | +------------------------------------------------+EVENT TIME: 09:55[EDT]| |NRC NOTIFIED BY: MIKE MORGAN |LAST UPDATE DATE: 10/18/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 +------------------------------------------------------------------------------+ | REACTOR TRIP CAUSED BY OPERATOR ERROR DURING TESTING OF THE REACTOR | | PROTECTION SYSTEM (RPS) | | | | MAINTENANCE TECHNICIANS WERE PERFORMING TRAIN B REACTOR TRIP BREAKER | | TESTING. AT THE SAME TIME, MONTHLY ANALOG OPERATIONAL TESTING WAS ALSO | | UNDERWAY ON CHANNEL #4 OF THE SOLID STATE PROTECTION SYSTEM (SSPS) WHICH IS | | PART OF TRAIN A. THE TESTING ON THE REACTOR TRIP BREAKERS CAUSED THE | | EXPECTED GENERAL WARNING ALARM FOR TRAIN B. WHILE REPOSITIONING THE | | MULTIPLEXER SWITCH FROM THE "A/B" POSITION TO THE NORMAL POSITION AS PART | | OF THE CHANNEL #4 TESTING, THE SWITCH WAS PASSED THROUGH THE INHIBIT | | POSITION. THIS CAUSED A GENERAL WARNING ALARM ON TRAIN A. THE COMBINATION | | OF THE TRAIN A AND TRAIN B GENERAL WARNING ALARMS CAUSED THE REACTOR TRIP. | | | | THE PLANT IS STABLE IN HOT STANDBY. ALL RODS FULLY INSERTED. DECAY HEAT | | IS BEING REMOVED AS NECESSARY BY DUMPING STEAM TO THE MAIN CONDENSER. | | AUXILIARY FEED IS SUPPLYING THE STEAM GENERATORS. | | | | OPERATIONS PERSONNEL WERE DEPENDING ON THE PEOPLE PERFORMING THE TWO | | MAINTENANCE ITEMS TO COORDINATE THEIR ACTIVITIES TO PREVENT A REACTOR TRIP. | | AS SUCH, THIS TRIP IS ATTRIBUTED TO PERSONNEL ERROR. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27917 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 10/18/94 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 14:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/18/94 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: HAMILTON |LAST UPDATE DATE: 10/18/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRISTENSEN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 | 0 | | 2 | N N 0 | 0 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SUPERVISOR WAS FOUND TO BE UNDER THE INFLUENCE OF ALCOHOL DURING A RANDOM | | TEST. THE EMPLOYEE HAS BEEN REMOVED FROM THE SITE, AND HAS BEEN REFERRED | | TO THE EMPLOYEE ASSISTANCE PROGRAM. SEE HOO LOG FOR ADDITIONAL DETAILS. | | THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27918 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 10/18/94 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 15:50 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/18/94 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: MARK GECKLE |LAST UPDATE DATE: 10/18/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FALSIFICATION OF PRE-EMPLOYMENT SCREENING. | | | | THE LICENSEE HAS DETERMINED THAT A CONTRACT EMPLOYEE FALSIFIED HIS | | PRE-EMPLOYMENT SECURITY SCREENING. THE CONTRACTOR IS EMPLOYED BY BARLETT | | NUCLEAR AND WORKED ONSITE AS AN INSULATOR. HIS SITE ACCESS BADGE HAS BEEN | | SUSPENDED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27919 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 10/18/94 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 20:25 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 10/18/94 | +------------------------------------------------+EVENT TIME: 16:57[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 10/18/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS START OF UNIT 3 EMERGENCY DIESEL GENERATORS. | | | | THE UNIT 3 EDG'S RECEIVED AN AUTO START SIGNAL AND THE THREE AVAILABLE | | UNIT 3 EDG'S STARTED AS REQUIRED. THE FOURTH UNIT 3 EDG WAS OUT OF SERVICE | | FOR ROUTINE TESTING. THE EDG'S DID NOT ACTUALLY LOAD ONTO THE EMERGENCY | | BUSES AND NO LOAD SHED OF ANY OF THE BUSES TOOK PLACE. THE ASSOCIATED | | EMERGENCY EQUIPMENT COOLING WATER PUMPS FOR THE EDG'S WERE ALREADY RUNNING | | WHEN THE ACTUATION OCCURRED AND WERE NOT CHALLENGED BY THE EVENT. | | | | THE CAUSE OF THE UNANTICIPATED ESF ACTUATION IS UNKNOWN AT THIS TIME BUT IS | | BELIEVED TO BE RELATED TO THE PERFORMANCE OF A CORE SPRAY LOGIC FUNCTIONAL | | TEST WHICH INVOLVED A CONTINUITY TEST OF THE AUTOSTART TEST SWITCH. THE | | UNIT 1 AND 2 EDG'S WERE UNAFFECTED BY THIS EVENT. THE EDG'S WERE SECURED | | AND RESET WITHIN APPROXIMATELY 10 MINUTES. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27920 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 10/18/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 20:55 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 10/18/94 | +------------------------------------------------+EVENT TIME: 18:55[CDT]| |NRC NOTIFIED BY: MIKE ENTWISTLE |LAST UPDATE DATE: 10/18/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B. CLAYTON RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | 2 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF PROTECTED AREA SECURITY LIGHTING. | | | | THE PROTECTED AREA PERIMETER LIGHTING WAS LOST AT 1855 CDT. COMPENSATORY | | ACTION WAS IMMEDIATELY TAKEN PER STATION PROCEDURES AND IN PLACE WITHIN | | SEVERAL MINUTES. THE SPECIFIC CAUSE IS UNKNOWN BUT HAS BEEN TRACED TO A | | TRIPPED 480 VOLT MCC BREAKER. ALL PERIMETER ALARM ZONES REMAINED | | FUNCTIONAL. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27921 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/19/94 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 04:41 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/18/94 | +------------------------------------------------+EVENT TIME: 23:35[PDT]| |NRC NOTIFIED BY: LEMKE |LAST UPDATE DATE: 10/19/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT LOST RHR DURING A DIESEL GENERATOR TEST DUE TO PERSONNEL ERROR. | | | | THIS OCCURRED DURING THE PERFORMANCE OF A DIESEL GENERATOR TEST WHICH | | REQUIRED THEM TO LOAD SHED. WHEN THEY STARTED LOAD SHEDDING ONE OF THE | | PIECES OF EQUIPMENT DROPPED WAS THE OPERATING RHR PUMP. THEY BELIEVE THE | | CAUSE WAS DUE TO PERSONNEL ERROR BECAUSE THE WRONG RHR PUMP WAS RUNNING. | | THE PUMP WAS RETURNED TO SERVICE WITHIN 6 MINS AND RCS TEMPERATURE | | INCREASED FROM 96 DEGREES TO 102 DEGREES. THEY ENTERED TS 3.4.1.4.2 WHICH | | REQUIRES AN RHR PUMP TO BE IMMEDIATELY STARTED WHEN THEY NO RHR PUMPS | | RUNNING. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+