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
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|Power Reactor |Event Number: 35700 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35701 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|General Information or Other |Event Number: 35702 |
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| 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 | |
| | |
| | |
| | |
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EVENT TEXT
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| 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.) |
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|Power Reactor |Event Number: 35703 |
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| 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
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| 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. |
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|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. |
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