U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/08/95 - 03/09/95 ** EVENT NUMBERS ** 28307 28440 28502 28503 28504 28505 28506 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28307 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 01/30/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 19:58 [ET]| |RX TYPE: [1] CE |EVENT DATE: 01/30/95 | +------------------------------------------------+EVENT TIME: 19:00[EST]| |NRC NOTIFIED BY: MCDOUGOLD |LAST UPDATE DATE: 03/08/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT 11 FIRE DAMPERS DID NOT MEET MANUFACTURERS | | SPECIFICATIONS AND WERE DECLARED INOPERABLE. | | | | ON 01/28/95 THE LICENSEE'S FIRE PROTECTION PERSONNEL STARTED AN AUDIT ON | | FIRE RELATED DAMPERS THAT WERE INSTALLED IN 1978. TODAY 16 DAMPERS WERE | | FOUND TO NOT MEET MANUFACTURERS SPECS. HOWEVER, FIVE OF THESE DAMPERS HAVE | | BEEN DETERMINED, BY ENGINEERING JUDGMENT, TO BE OPERABLE. THE OTHER 11 | | DAMPERS, HOWEVER, MAY NOT SHUT DURING A FIRE. AN ENGINEERING EVALUATION | | WILL BE MADE ON THESE 11 DAMPERS. UNTIL THEN, THE LICENSEE HAS DECLARED | | THESE DAMPERS INOPERABLE, PLACING THE UNIT IN A TS LCO REQUIRING THE | | LICENSEE TO MAINTAIN A ROVING FIRE WATCH UNTIL THE PROBLEM IS CORRECTED. | | THE RI WILL BE INFORMED. | | | | * * * UPDATE AT 1458 ON 03/08/95 BY EBERT ENTERED BY HOO JOLLIFFE * * * | | | | THE LICENSEE AUDIT MENTIONED ABOVE HAD IDENTIFIED THAT THE 11 FIRE | | DAMPERS IN QUESTION HAD NOT BEEN INSTALLED IN STRICT CONFORMANCE WITH | | MANUFACTURER'S DRAWINGS. THE DOCUMENTATION OF THE INSTALLATION DEVIATIONS | | FROM THE MANUFACTURER'S DRAWINGS WERE REVIEWED AND DETERMINED TO BE | | SATISFACTORY IN NRC INSPECTION REPORT #50-309/8104. LICENSEE ENGINEERING | | EVALUATION #092-95 DETERMINED THAT THESE 11 INSTALLED FIRE DAMPERS WERE NOT | | OUTSIDE THE DESIGN BASIS. THUS, LICENSEE DESIRES TO RETRACT THIS EVENT. | | LICENSEE DOES NOT PLAN TO SUBMIT AN LER ON THIS EVENT TO THE NRC. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R1DO JOYNER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28440 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 02/25/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 12:37 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/25/95 | +------------------------------------------------+EVENT TIME: 11:22[EST]| |NRC NOTIFIED BY: OLSEN |LAST UPDATE DATE: 03/09/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -RCS TEMP DECREASED, PZR LEVEL DROPPED, CVCS LETDOWN ISOLATED DURING A TEST | | | | AT 1122, DURING THE PERFORMANCE OF AN AUXILIARY FEEDWATER SYSTEM FLOW TEST, | | A LARGE FLOWRATE CAUSED THE REACTOR COOLANT SYSTEM TEMPERATURE TO DECREASE | | FROM 547 TO 542 DEGREES F AND THE PRESSURIZER WATER LEVEL TO DROP FROM | | 24% TO 17.2%. | | | | THE CHEMICAL AND VOLUME CONTROL LETDOWN SYSTEM AUTOMATICALLY ISOLATED WHEN | | THE PRESSURIZER LEVEL DROPPED TO 17.2%. | | | | AT 1134, REACTOR COOLANT SYSTEM TEMPERATURE AND LEVEL RETURNED TO NORMAL | | AND PLANT OPERATORS RESET THE LETDOWN SYSTEM. | | | | LICENSEE IS INVESTIGATING THE CAUSE AND WILL PROBABLY REVISE THE TEST | | PROCEDURE. | | | | LICENSEE NOTIFIED LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 0253 3/9/95 BY SAUER TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE CVCS LETDOWN ISOLATION | | REPORTED IN THE NOTIFICATION IS NOT CONSIDERED TO BE AN ESF ACTUATION. THE | | LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28502 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/08/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:45 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/23/95 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: MURPHY |LAST UPDATE DATE: 03/08/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -FLOW ARROW ON NUPRO 1/4 INCH LIFT CHECK VALVES POINTS IN WRONG DIRECTION- | | | | ON 01/23/95, LICENSEE DETERMINED THAT TEN NUPRO MODEL SS-53S4 1/4 INCH LIFT | | CHECK VALVES PURCHASED IN 08/94 HAD THE FLOW ARROW MARKED ON THE VALVE BODY | | POINTING IN THE WRONG DIRECTION. NONE OF THESE VALVES HAVE BEEN INSTALLED | | IN THE PLANT. | | | | NUPRO BELIEVES THIS CONDITION TO BE CAUSED BY HUMAN ERROR. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | CONTACT NRR WALTER HAASS FOR FURTHER DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28503 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 03/08/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/08/95 | +------------------------------------------------+EVENT TIME: 12:00[CST]| |NRC NOTIFIED BY: STRACKA |LAST UPDATE DATE: 03/08/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE SHAFER RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - UNIT 2 IN MODE 5 WITH 2 OF 2 EDGs INOP & SHARED EDG IN STANDBY - | | | | ZION STATION HAS A TOTAL OF 5 EDGs; 2 FOR EACH UNIT AND A SHARED EDG (#0). | | | | UNIT 2 IS IN MODE 5 (COLD SHUTDOWN) IN A REFUELING OUTAGE WITH #2B EDG | | INOPERABLE AND BEING REPAIRED. CONTROL ROOM OPERATORS MANUALLY TRIPPED | | #2A EDG DUE TO SMOKE COMING FROM #7R & #8R CYLINDERS DURING A 24 HOUR | | ENDURANCE RUN AND DECLARED THE #2A EDG INOPERABLE. #0 EDG IS IN STANDBY | | MODE ALIGNED FOR UNITS 1 AND 2. | | | | UNIT 1 IS AT 100% POWER AND UNAFFECTED BY THIS EVENT WITH #1A AND #1B EDGs | | OPERABLE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28504 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 03/08/95 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 17:21 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 03/08/95 | +------------------------------------------------+EVENT TIME: 14:45[CST]| |NRC NOTIFIED BY: MARTIN |LAST UPDATE DATE: 03/08/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - Rx TRIP BREAKERS OPENED DURING A Rx TRIP BREAKER TIME RESPONSE TEST - | | | | WHILE PERFORMING A TIME RESPONSE SURVEILLANCE TEST OF THE REACTOR TRIP | | BREAKERS AT 100% POWER, CONTROL ROOM OPERATORS POSITIONED THE MAIN CONTROL | | BOARD SWITCH TO THE CLOSE POSITION TO CLOSE THE REACTOR TRIP BREAKER, | | THE REACTOR TRIP BREAKERS OPENED UNEXPECTEDLY TRIPPING THE REACTOR AND | | THE MAIN TURBINE. LICENSEE IS INVESTIGATING THE CAUSE. | | | | ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING DUMPED TO THE | | ATMOSPHERE VIA THE ATMOSPHERIC RELIEF VALVES. THE PLANT IS STABLE IN | | MODE 3 (HOT STANDBY). | | | | FOLLOWING THE Rx TRIP, 13.8 KV NON VITAL BUS #PA-01 FAILED TO SWAP TO THE | | STARTUP TRANSFORMER CAUSING THE LOSS OF 1 OF 3 OPERATING REACTOR COOLANT | | PUMPS. LICENSEE IS INVESTIGATING THE CAUSE. TECH SPEC LCO A/S 3.4.1.2 | | REQUIRES LICENSEE TO RESTORE THE ONE INOPERABLE Rx COOLANT PUMP TO OPERABLE | | STATUS WITHIN 72 HOURS OR PLACE THE PLANT IN AT LEAST HOT SHUTDOWN MODE | | WITHIN THE NEXT 12 HOURS. | | | | #PA-01 FAILING TO SWAP TO THE S/U TRANSFORMER ALSO CAUSED THE LOSS OF | | 1 OF 2 OPERATING CIRC WATER PUMPS. TWO OPERATING CIRC WATER PUMPS ARE | | REQUIRED TO MAINTAIN VACUUM IN THE MAIN CONDENSER. CONTROL ROOM OPERATORS | | TRIPPED THE SECOND OPERATING CIRC WATER PUMP. THE THIRD CIRC WATER PUMP | | WAS INOPERABLE FOR REPAIRS. | | | | FOLLOWING THE Rx TRIP, THE AFW SYSTEM STARTED, AS EXPECTED. HOWEVER, | | THE TURBINE DRIVEN AFW PUMP WATER LEVEL CONTROL VALVE #AL-HV-10 TO THE | | 'B' STEAM GENERATOR WOULD NOT FULLY CLOSE. CONTROL ROOM OPERATORS MANUALLY | | CLOSED THE VALVE AND DECLARED IT INOPERABLE. TECH SPEC LCO A/S 3.7.1.2 | | REQUIRES LICENSEE TO RESTORE THIS VALVE TO OPERABLE STATUS WITHIN 72 HOURS | | OR TO PLACE THE PLANT IN AT LEAST HOT SHUTDOWN MODE WITHIN THE NEXT 6 | | HOURS. | | | | THE CONTROL ROOM VENTILATION SYSTEM SHIFTED TO EMERGENCY MODE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | LICENSEE PLANS TO ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28505 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 03/08/95 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 20:21 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/08/95 | +------------------------------------------------+EVENT TIME: 17:42[CST]| |NRC NOTIFIED BY: BARTON |LAST UPDATE DATE: 03/08/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE SHAFER 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PCIS GROUP 3A ISOLATION DURING INSTALLATION OF TEMPORARY PLANT MOD - | | | | WHILE INSTALLING A TEMPORARY PLANT MODIFICATION FOR CORRECTIVE AND | | PREVENTATIVE MAINTENANCE WORK, I & C TECHNICIANS WERE LIFTING LEADS WHEN A | | NEUTRAL LEAD LOST CONTACT CAUSING A PRIMARY CONTAINMENT ISOLATION SYSTEM | | GROUP 3A ISOLATION (PRIMARY CONTAINMENT ISOLATION VALVES CLOSED AND | | REACTOR BUILDING VENTILATION DAMPERS CLOSED). | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT 28494. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28506 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 03/09/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 05:30 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 03/09/95 | +------------------------------------------------+EVENT TIME: 04:35[EST]| |NRC NOTIFIED BY: DALL'AU |LAST UPDATE DATE: 03/09/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |COLLINS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 60 POWER OPERATION | 60 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INTAKE COOLING WATER SYSTEM FLOW DECREASED TO BELOW MINIMUM ACCEPTABLE | | LEVEL DUE TO FOULING BY AQUATIC GRASSES. | | | | THE FLOW RATE THROUGH THE INTAKE COOLING WATER SYSTEM DECREASED TO BELOW | | THE MINIMUM REQUIRED FLOW RATE DUE TO EXTENSIVE FOULING OF THE INTAKE | | STRUCTURE BY AQUATIC GRASSES DISLODGED BY RECENT STORM ACTIVITY AT THE | | SITE. THE INTAKE COOLING WATER SYSTEM PROVIDES A HEAT SINK TO BOTH THE | | COMPONENT COOLING WATER AND TURBINE PLANT COOLING WATER SYSTEM. THE | | LICENSEE HAS BEEN CONTINUOUSLY BACKWASHING THE TRAVELING SCREENS IN THE | | INTAKE STRUCTURE TO INCREASE FLOW THROUGH THE SYSTEM. AT 0521, FLOW | | THROUGH THE INTAKE COOLING WATER SYSTEM INCREASED ABOVE THE MINIMUM | | REQUIRED FLOW RATE. | | | | THE LICENSEE IS CURRENTLY ATTEMPTING TO DEVELOP A COURSE OF ACTION WITH | | REGARD TO THIS PROBLEM. THE UNIT IS CURRENTLY OPERATING AT A REDUCED POWER | | LEVEL DUE TO SIMILAR FOULING OF THE PLANT CIRCULATING WATER SYSTEM. THE | | NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+