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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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                            |
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