United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2003 > February 3

Event Notification Report for February 3, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           01/31/2003 - 02/03/2003



                              ** EVENT NUMBERS **



39551  39552  39553  39554  



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39551       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 01/31/2003|

|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 19:55[EST]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        01/30/2003|

+------------------------------------------------+EVENT TIME:        13:00[EST]|

| NRC NOTIFIED BY:  SOSSON                       |LAST UPDATE DATE:  01/31/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DANIEL HOLODY        R1      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| PLANT IN UNANALYZED CONDITION DUE TO INCORRECT INSTALLATION OF DRAIN SYSTEM  |

| CLEANOUT PLUG                                                                |

|                                                                              |

| "At 13:00 EST on 1/31/2003, a system manager discovered a dirty radwaste     |

| floor drain system cleanout plug installed incorrectly in the Unit 1 A/C RHR |

| room.  The threads on cleanout plug were found not engaged.  The plug was    |

| immediately installed terminating the condition.   No check valves are       |

| installed in this cleanout line and therefore significant back leakage could |

| occur into the RHR room.                                                     |

|                                                                              |

| "This event resulted in a condition that could have rendered all trains of   |

| the RHR system inoperable during a flooding event by bypassing the normal    |

| floor drain system.                                                          |

|                                                                              |

| "The time that this condition began is not currently known, pending          |

| investigation.   A walk down of similar drains on both units is being        |

| conducted."                                                                  |

|                                                                              |

| The NRC Resident Inspector will be notified.                                 |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39552       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 02/01/2003|

|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 04:35[EST]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/01/2003|

+------------------------------------------------+EVENT TIME:        02:33[CST]|

| NRC NOTIFIED BY:  ROBERT TEMPLE                |LAST UPDATE DATE:  02/01/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK RING            R3      |

|10 CFR SECTION:                                 |                             |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     M/R        Y       50       Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| MANUAL REACTOR SCRAM DUE TO CONDENSER  TUBE LEAK                             |

|                                                                              |

| "Inserted a manual reactor scram due to a condenser tube leak resulting in   |

| high condenser, feedwater and reactor water conductivity. "                  |

|                                                                              |

| All control rods inserted into the core.  There were no openings of          |

| power-operated relief valves, relief valves, code safeties, or dump valves.  |

| Cooldown is being accomplished via the Reactor cleanup to condenser system.  |

| All safety systems operated as expected.  The switchyard is in a stable      |

| condition.                                                                   |

|                                                                              |

| The NRC Resident Inspector was notified by the Licensee.                     |

|                                                                              |

| *** UPDATE ON 2/2/03 AT 0044 EST FROM MARK GILBERT TO HOWIE CROUCH VIA       |

| FACSIMILE ***                                                                |

|                                                                              |

| "DAEC [Duane Arnold Energy Center] is making an addendum to EN [Event        |

| Number] #39552 made on 2/1/2003 at 0233. EN #39552 reported the insertion of |

| a manual scram due to a condenser tube leak which was reportable under 10    |

| CFR 50.72(b)(2)(iv)(B) for an RPS actuation. Following the insertion of the  |

| reactor scram, reactor water level dropped below 170 [inches] and PCIS       |

| [Primary Containment Isolation Signal] groups 2,3, and 4 were received.  All |

| isolations went to completion. The reactor water level drop is normal        |

| following a reactor scram due to the void collapse in the reactor vessel.    |

| Reactor water level was restored.  Currently the plant is stable in Mode 4   |

| and maintaining a normal reactor water level band.  DAEC is currently making |

| plans to determine the source of the condenser tube leak.                    |

|                                                                              |

| "This addendum report is being made under [10 CFR] 50.72(b)(3)(iv)(A), 'Any  |

| event or condition that results in valid actuation of any systems listed in  |

| paragraph (b)(3)(iv)(B) of this section.' as a result of the PCIS groups 2   |

| (Radwaste and TIP [Tranverse Incore Probe] system) and 3 (Containment        |

| atmosphere control system)."                                                 |

|                                                                              |

| The NRC Resident Inspector was notified of the addendum by the licensee.     |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39553       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 02/01/2003|

|    UNIT:  [] [2] []                 STATE:  CA |NOTIFICATION TIME: 09:25[EST]|

|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        02/01/2003|

+------------------------------------------------+EVENT TIME:        03:10[PST]|

| NRC NOTIFIED BY:  MATTHEW THURBURN             |LAST UPDATE DATE:  02/01/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JONES        R4      |

|10 CFR SECTION:                                 |                             |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| MAIN GENERATOR LOSS OF EXCITATION CAUSES A TURBINE TRIP THEN A REACTOR TRIP  |

|                                                                              |

| A loss of main generator excitation caused a turbine trip and, subsequent to |

| that, a reactor trip.  During the trip sequence, a non-1E electrical bus     |

| experienced low voltage and automatically transferred to an auxiliary bus.   |

| During the transfer, both Main Feedwater Pump (MFP) oil pumps tripped        |

| causing a trip of both MFPs.  The loss of Main Feedwater caused low steam    |

| generator levels which initiated the Emergency Feedwater Actuation System    |

| (EFAS).  EFAS restored steam generator levels to normal.                     |

|                                                                              |

| All control rods inserted into the core. No power-operated relief valves,    |

| relief valves or code safeties lifted during the trip.  The plant is         |

| removing decay heat via the steam dump to condenser system.  The electrical  |

| grid is stable.  The other at the site was not affected.                     |

|                                                                              |

| The cause of the loss of generator excitation is under investigation.        |

|                                                                              |

| The NRC Resident Inspector was notified of the event by the Licensee.        |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39554       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 02/01/2003|

|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 09:41[EST]|

|   RXTYPE: [2] GE-4                             |EVENT DATE:        02/01/2003|

+------------------------------------------------+EVENT TIME:        01:45[EST]|

| NRC NOTIFIED BY:  JEFF GROFF                   |LAST UPDATE DATE:  02/01/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK RING            R3      |

|10 CFR SECTION:                                 |                             |

|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| LOSS OF A SAFETY FUNCTION DUE TO ALL FOUR EMERGENCY DIESEL GENERATORS BEING  |

| DECLARED INOPERABLE                                                          |

|                                                                              |

| The following information was received from the Licensee via facsimile:      |

|                                                                              |

| "At 0145 hours [EST] on 2/1/2003, all four Emergency Diesel Generators       |

| (EDGs) were declared inoperable following discovery of a Fuel Oil leakage    |

| drain path change that was installed to prevent Fuel Oil leakage from        |

| reaching the ground water.                                                   |

|                                                                              |

| "This change involved the installation of plastic sleeves on the fuel oil    |

| drains for all four EDGs to reroute the fuel oil drains to a catch basin.    |

| The normal drain path is through the RHR [Residual Heat Removal] Complex     |

| (which houses the EDGs) drain system to the chemical pond.  This change was  |

| installed after a crack was discovered in a 21 inch concrete line in the     |

| drain path from the RHR Complex Drain Sump to the Chemical Pond. This change |

| was installed on 01/17/03.                                                   |

|                                                                              |

| "While running EDG 11 for post maintenance testing following a scheduled     |

| maintenance outage, fuel oil in a drain sleeve backed up and spilled out of  |

| a vent on the fuel oil drain header.  This spillage resulted in a small      |

| lagging fire.  EDG 11 was immediately shutdown and the fire was extinguished |

| within a few minutes.  No significant damage to EDG 11 was caused by the     |

| fire.  Since all four EDGs had a similar fuel oil drain configuration, they  |

| were declared inoperable at 0145 hours and Technical Specification 3.8.1,    |

| Condition B was entered, which requires restoration of one division of the   |

| EDGs within 2 hours.                                                         |

|                                                                              |

| "At 0329 hours, the normal fuel oil drain configuration was restored for EDG |

| 13 and EDG 14 (Division 2) and Technical Specification 3.8.1, Condition B    |

| was exited.  At 0345 hours, the normal fuel oil drain configuration was      |

| restored for EDG 12 (Division 1). EDG 11 remains inoperable until the        |

| completion of post maintenance testing.                                      |

|                                                                              |

| "This notification is being made in accordance with 10CFR50.72(b)(3)(v)[(D)] |

| due to all four EDGs being inoperable causing the loss of a safety           |

| function."                                                                   |

|                                                                              |

| The fire was extinguished without offsite assistance and there were no       |

| injuries due to the fire.                                                    |

|                                                                              |

| The Licensee has notified the NRC Resident Inspector.                        |

+------------------------------------------------------------------------------+