Event Notification Report for May 12, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/11/1999 - 05/12/1999 ** EVENT NUMBERS ** 35700 35701 35702 35703 35704 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35700 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/11/1999| | UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 14:20[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/11/1999| +------------------------------------------------+EVENT TIME: 13:20[EDT]| | NRC NOTIFIED BY: VASELY |LAST UPDATE DATE: 05/11/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CURTIS COWGILL R1 | |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CENTRAL CONTROL ROOM (CCR) TOXIC GAS MONITOR SETPOINTS MAY DRIFT BEYOND TECH | | SPEC (TS) LIMITS. | | | | DURING AN ENGINEERING EVALUATION OF TOXIC GAS MONITOR SETPOINTS, IT WAS | | DETERMINED THAT AMMONIA MONITOR DRIFT COULD POSSIBLY CAUSE THE PLANT TO | | EXCEED THEIR TS ACTUATION LIMIT. CURRENTLY, THEIR SETPOINT FOR AMMONIA | | ACTUATION IS 21 PPM (TS LIMIT IS 25 PPM), AND THE CALCULATED DRIFT OCCURRING | | IN ONE QUARTERLY PERIOD WOULD BE 18 PPM. ADDING THE TWO VALUES (21 PPM AND | | 18 PPM) WOULD RESULT IN THE PLANT EXCEEDING ITS TS LIMITS, PUTTING THE PLANT | | INTO AN LCO ACTION STATEMENT. | | | | AS REQUIRED BY TS ACTION STATEMENT, THE CCR VENTILATION SYSTEM WAS PLACED IN | | INTERNAL RECIRCULATION (INCIDENT MODE) AT 1323 TO RESTORE TO DESIGN AND EXIT | | THE LCO ACTION STATEMENT. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35701 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 05/11/1999| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 15:20[EDT]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 05/11/1999| +------------------------------------------------+EVENT TIME: 13:25[CDT]| | NRC NOTIFIED BY: ANDERSON |LAST UPDATE DATE: 05/11/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 | |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE PERFORMING A HEAVY LOAD LIFT OVER AN OPEN FUELED REACTOR VESSEL, THE | | PLANT WENT OUTSIDE ITS DESIGN BASIS. | | | | ON 05/12/99, THE LICENSEE DETERMINED THAT, DURING AN EVOLUTION ON 05/08/99, | | THE UPPER INTERNALS (A "HEAVY LOAD") WAS TRANSPORTED OVER THE OPEN UNIT 1 | | REACTOR, WHICH CONTAINED FUEL, WHILE THE CONTAINMENT IN-SERVICE PURGE WAS | | OPERATING. THE USAR STATES: "DURING HEAVY LOAD LIFTS OVER THE OPEN FUELED | | REACTOR VESSEL, AT LEAST ONE ISOLATION VALVE WILL BE CLOSED IN EACH LINE | | PENETRATING THE CONTAINMENT ATMOSPHERE TO THE OUTSIDE." THE UNIT WAS, | | THEREFORE, OUTSIDE THE DESIGN BASIS SINCE NO ISOLATION VALVES FOR THE | | IN-SERVICE PURGE PENETRATIONS WERE CLOSED DURING THIS EVOLUTION. THE HEAVY | | LOAD MOVEMENT WAS COMPLETED WITHOUT INCIDENT. NOTE THAT THE IN-SERVICE | | PURGE DISCHARGE IS FILTERED, AND THE AUTOMATIC ISOLATION OF THESE | | PENETRATIONS, UPON HIGH RADIATION, WAS OPERABLE. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35702 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: NC DEPT OF ENV & NAT RESOURCES |NOTIFICATION DATE: 05/11/1999| |LICENSEE: NELLO L. TEER COMPANY |NOTIFICATION TIME: 16:30[EDT]| | CITY: REGION: 2 |EVENT DATE: 05/10/1999| | COUNTY: MARTIN STATE: NC |EVENT TIME: 16:22[EDT]| |LICENSE#: 032-0789-1 AGREEMENT: Y |LAST UPDATE DATE: 05/11/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |RUDOLPH BERNHARD R2 | | |JOE HOLONICH NMSS | +------------------------------------------------+FRANK CONGEL IRO | | NRC NOTIFIED BY: COX (NCDENR) | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |NDAM DAMAGED GAUGE/DEVICE | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED TROXLER GAUGE IN MARTIN COUNTY, NORTH CAROLINA - INCIDENT #99-07 | | | | THE NORTH CAROLINA DIVISION OF RADIATION PROTECTION (NCDRP) WAS NOTIFIED BY | | A NORTH CAROLINA REGISTERED CONSULTANT THAT A STATE LICENSED COMPANY (NELLO | | L. TEER COMPANY) HAD ONE OF THEIR TROXLER GAUGES RUN OVER BY A COMPANY TRUCK | | IN MARTIN COUNTY, NORTH CAROLINA. THE INITIAL INFORMATION ON THE DAMAGE WAS | | THAT ONLY THE GAUGE HANDLE WAS BROKEN OFF. IT WAS DETERMINED, AT THAT TIME, | | THAT THE INCIDENT DID NOT MEET QUALIFICATIONS FOR A 24-HOUR NOTIFICATION. | | SINCE THE OPERATOR HAD STORED THE GAUGE BACK IN ITS TRANSPORT CASE, THE | | CONSULTANT AND LICENSEE AUTHORIZED THE RETURN OF THE TRUCK AND GAUGE TO THE | | LICENSEE'S DURHAM, NORTH CAROLINA, FACILITY. | | | | ON 05/10/99. A SURVEY OF THE GAUGE WITH AN IONIZATION METER WAS MADE, AND | | READINGS AS HIGH AS 123 mR/HR WERE MEASURED AT THE FRONT OF THE CASE. UPON | | OPENING THE CASE, IT WAS DISCOVERED THAT THE GAUGE HAD CONSIDERABLE DAMAGE | | WITH THE SOURCE ROD SEPARATED FROM THE GAUGE AND THE GAUGE IN SEVERAL | | PIECES. IT WAS FURTHER DETERMINED THAT THE SOURCE WAS FREE OF ANY | | CONTAMINATION. | | | | THE EXPOSURE RECORD OF THE OPERATOR'S FILM BADGE SHOWED THAT HE HAD RECEIVED | | 60 mR (SHALLOW AND DEEP) FOR THE PERIOD STARTING 04/01/99. | | | | THE INCIDENT IS STILL BEING INVESTIGATED BY BOTH THE LICENSEE AND THE | | NCDRP. | | | | (CALL THE NRC OPERATIONS OFFICER FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35703 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 05/11/1999| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 16:41[EDT]| | RXTYPE: [1] GE-2 |EVENT DATE: 05/11/1999| +------------------------------------------------+EVENT TIME: 16:00[EDT]| | NRC NOTIFIED BY: AMES |LAST UPDATE DATE: 05/11/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CURTIS COWGILL R1 | |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LEAD SHIELDING INSTALLED ON FUEL POOL COOLING SYSTEM PIPING CAUSES HANGER | | DESIGN CRITERIA TO BE EXCEEDED. | | | | DURING A REVIEW OF CALCULATIONS FOR PIPE HANGERS AND SUPPORTS ASSOCIATED | | WITH FUEL POOL COOLING SYSTEM PIPING, IT WAS DETERMINED THAT PIPE SUPPORTS | | PS-13 AND 14 DO NOT MEET THE DESIGN CRITERIA OF ANSI B31.1 1955. HOWEVER, | | THEY DO MEET THE OPERABILITY REQUIREMENTS OF NRC GENERIC LETTER 91-18. | | SINCE THIS SYSTEM IS STILL OPERABLE, NO COMPENSATORY ACTIONS ARE REQUIRED AT | | THIS TIME. THE CONDITION WAS CAUSED BY A PRIOR INSTALLATION OF LEAD | | SHIELDING ON THE PIPING. THE LICENSEE'S CORRECTIVE ACTION IS TO EVALUATE | | THE SUPPORTS FOR MODIFICATIONS OR REMOVE THE ADDED LEAD SHIELDING FROM THE | | PIPING. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35704 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 05/12/1999| | UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 03:59[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 05/12/1999| +------------------------------------------------+EVENT TIME: 00:38[CDT]| | NRC NOTIFIED BY: DAVE DEES |LAST UPDATE DATE: 05/12/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHARLES CAIN R4 | |10 CFR SECTION: |JOSE CALVO NRR | |AESF 50.72(b)(2)(ii) ESF ACTUATION |FRANK CONGEL IRO | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 55 Power Operation |55 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PARTIAL LOSS OF OFFSITE POWER (ONE OF THREE SOURCES) DUE TO A TRANSFORMER | | LOCKOUT | | | | At 0038 CDT, the east bus (345 kV) was lost due to a lockout on the #7 | | transformer. The loss of the east bus resulted in the loss of normal power | | to the 'A' safeguards 4160V bus. On loss of power to the #7 transformer, a | | shutdown sequencer actuation occurred due to low power. This caused the | | 'A' emergency diesel generator to automatically start and load the bus. The | | following equipment also automatically started: 'A' centrifugal charging | | pump, 'A' component cooling water pump, 'A' essential service water pump, | | 'A' control room air conditioning unit, 'A' class 1E air conditioning unit, | | 'A' motor-driven auxiliary feedwater pump, 'A' and 'C' containment coolers, | | and the turbine-driven auxiliary feedwater pump. The licensee stated that | | all systems functioned as required and that there was nothing unusual or not | | understood. | | | | At 0058 CDT, the licensee reset the #7 transformer lockout, and the east bus | | was restored to service at 0059 CDT. At 0244 CDT, the licensee re-energized | | the #7 transformer (the normal power feed to the safeguards bus | | transformer), and normal offsite power was restored to the 'A' emergency bus | | at 0256 CDT. | | | | The transformer lockout was initially believed to be caused by a lightening | | strike and was later determined to be caused by a raccoon. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021