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Event Notification Report for October 18, 2001

                    *** NOT FOR PUBLIC DISTRIBUTION***
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/17/2001 - 10/18/2001

                              ** EVENT NUMBERS **

38398  38399  38400  38402  
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| *** NOT FOR PUBLIC DISTRIBUTION ***                                          |
|Power Reactor                                    |Event Number:   38398       |
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| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 10/17/2001|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 10:44[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/17/2001|
+------------------------------------------------+EVENT TIME:        06:11[CDT]|
| NRC NOTIFIED BY:  PRICE                        |LAST UPDATE DATE:  10/17/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTON VEGEL          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       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR WAS MANUALLY SCRAMMED FROM 100% POWER.                               |
|                                                                              |
| At approximately 0610 on October 17, Instrument AC bus 1Y11 failed due to an |
| inverter failure.  One of the two reactor feed pumps tripped due to a low    |
| suction pressure caused by its minimum flow valve failing open on the loss   |
| of instrument power.  The Reactor was then manually scrammed in anticipation |
| of a Reactor low level trip.   All rods were inserted, no relief valves      |
| lifted and the plant response was as designed with the exception that one    |
| main generator breaker failed to trip (the transmission system isolated the  |
| generator as designed).  Containment isolation Groups 2 through 4 were       |
| initiated when reactor level decreased below 170 above top of active fuel    |
| and a Group 5 isolation was initiated by the loss of instrument power.       |
| Reactor level was restored and maintained using the RCIC system initially    |
| (auto initiation) and subsequently the reactor feed system.  The plant is    |
| currently in Mode 3 with plans to go to Mode 4.                              |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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|Power Reactor                                    |Event Number:   38399       |
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| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 10/17/2001|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 11:10[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/17/2001|
+------------------------------------------------+EVENT TIME:        02:48[CDT]|
| NRC NOTIFIED BY:  DAVID YOUNG                  |LAST UPDATE DATE:  10/17/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BILL JONES           R4      |
|10 CFR SECTION:                                 |                             |
|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     N          Y       80       Power Operation  |80       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| UNEXPECTED  LOSS OF POWER TO A SAFETY-RELATED SWITCHGEAR                     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At approximately 2:48 am CDT, the normal supply breaker to the Division 2   |
| 4160-volt safety-related switchgear opened unexpectedly, causing a loss of   |
| power to the Division 2 electrical systems.  This event is being reported in |
| accordance with 10CFR50.72(b)(3)(iv)(A) as a valid actuation of safety       |
| systems."                                                                    |
|                                                                              |
| "The Division 2 diesel generator responded as expected by automatically      |
| starting and restoring power to the Division 2 switchgear.  Also,            |
| containment isolation valves actuated as expected in the following systems   |
| due to the loss of power:  reactor water cleanup, reactor building floor and |
| equipment drains, reactor coolant sampling, containment airlock air supply,  |
| and containment ventilation systems.  Automatic actuations occurred as       |
| expected in the following systems:  standby gas control, annulus mixing,     |
| control building ventilation, and fuel building ventilation."                |
|                                                                              |
| "Following the event, the containment isolation logic was reset and          |
| ventilation systems were returned to their normal configuration."            |
|                                                                              |
| "The Division 2 diesel generator remains in service supplying the Division 2 |
| switchgear.  The cause of the trip of the normal supply breaker to the       |
| 4160[-volt] standby switchgear is being investigated."                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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| *** NOT FOR PUBLIC DISTRIBUTION ***                                          |
|Power Reactor                                    |Event Number:   38400       |
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| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 10/17/2001|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 15:05[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        10/17/2001|
+------------------------------------------------+EVENT TIME:        06:50[EDT]|
| NRC NOTIFIED BY:  STEVE MORRISEY               |LAST UPDATE DATE:  10/17/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION DUE TO SMALL OIL SPILL                                  |
|                                                                              |
| The licensee notified the New Hampshire Environmental Services of an oil     |
| spill of less than or equal to 25 gallons.  There was no oil discharged from |
| the site nor did any enter a waterway.   Also, no impact to groundwater was  |
| observed.  The licensee is removing the contaminated soil.                   |
|                                                                              |
| The licensee is in the process of replacing some oil bearing piping.  A      |
| section of that piping contained residue of oil, which was washed out by     |
| heavy rains yesterday.  The amount of oil is small and this notification is  |
| conservative  based on the fact that it was not possible to accurately       |
| determine the quantity.  Oil was observed in the rainwater inside an         |
| excavation.                                                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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| *** NOT FOR PUBLIC DISTRIBUTION ***                                          |
|Power Reactor                                    |Event Number:   38402       |
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| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 10/17/2001|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 17:56[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/17/2001|
+------------------------------------------------+EVENT TIME:        14:02[CDT]|
| NRC NOTIFIED BY:  JAMES DEDIC                  |LAST UPDATE DATE:  10/17/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BILL JONES           R4      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| HPSI SYSTEM DECLARED INOPERABLE.                                             |
|                                                                              |
| "At 1415 on 10/17/01, the HPCI steam stop valve did not reopen upon release  |
| of the local turbine trip knob. This condition was discovered during         |
| surveillance testing. The surveillance procedure directs declaring the HPCI  |
| system inoperable if this condition occurs. The HPCI system was originally   |
| declared inoperable at 1402 on 10/17/01 for surveillance testing. This is    |
| being reported as a failure of a single train system such that it cannot     |
| perform its safety function of mitigating the consequences of an accident.   |
| All other Emergency Core Cooling Systems are operable. This event is being   |
| entered into the corrective action and work control programs for             |
| investigation and resolution."                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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