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Event Notification Report for January 7, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/04/2002 - 01/07/2002

                              ** EVENT NUMBERS **

38513  38602  38607  38608  38609  38610  38611  

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|Power Reactor                                    |Event Number:   38513       |
+------------------------------------------------------------------------------+
                         
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| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 11/23/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 12:30[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/23/2001|
+------------------------------------------------+EVENT TIME:        12:10[EST]|
| NRC NOTIFIED BY:  CHARLIE PIKE                 |LAST UPDATE DATE:  01/06/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CAUDLE JULIAN        R2      |
|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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO FLORIDA STATE INVOLVING RECOVERED SEA TURTLE
FROM    |
| UNIT 1 INTAKE STRUCTURE                                                      |
|                                                                              |
| "A sea turtle with no external injuries but appearing to be distressed was   |
| recovered from the Unit 1 Intake Structure.  The State Stranding Coordinator |
| for sea turtles has been contacted."                                         |
|                                                                              |
| * * * UPDATE 11/23/01 AT 1255EST FROM CHARLIE PIKE TO S. SANDIN * * *        |
|                                                                              |
| "Turtle has died."                                                           |
|                                                                              |
| The licensee informed both the State of Florida and the NRC Resident         |
| Inspector.                                                                   |
|                                                                              |
| * * * UPDATE 1413EST ON 12/3/01 FROM JACK BREEN TO FANGIE JONES * * *        |
|                                                                              |
| At approximately 1215 EST on 12/3/01, a report was made to the Florida       |
| Department of Fish and Wildlife concerning the recovery of an injured sea    |
| turtle from the plant's intake canal.  The turtle was a green sea turtle in  |
| the intake canal that appeared distressed and looked to have a wound from a  |
| boat motor on its back.  It will be transferred to the State for             |
| rehabilitation.                                                              |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  Notified           |
| R2DO(MacAlpine).                                                             |
|                                                                              |
| * * * UPDATE 1333EST ON 12/15/01 FROM JACK BREEN TO JOHN MACKINNON * * *     |
|                                                                              |
| At approximately 1215 EST on 12/15/01, a report was made to the Florida      |
| Department of Fish and Wildlife Conservation Commission to pick up a Green   |
| Turtle for rehabilitation. The Green Turtle was taken from the plant's       |
| intake canal, and the turtle appears to have shark bites.                    |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  Notified R2DO      |
| (Chuck Ogle).                                                                |
|                                                                              |
| * * * UPDATE 1450EST ON 01/06/02 FROM TULLIDGE TO JOHN MACKINNON * * *       |
|                                                                              |
| At 1350EST, a notificaiton to the State of Florida Department of Fish and    |
| Wildlife Conservation Commission was made due to finding an injured          |
| Loggerhead sea turtle in Unit 1 intake. The sea turtle was transported       |
| offsite for rehabilitation. R2DO (Tom Decker) notified.                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38602       |
+------------------------------------------------------------------------------+
                         
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| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 01/01/2002|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 10:08[EST]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        01/01/2002|
+------------------------------------------------+EVENT TIME:        09:19[EST]|
| NRC NOTIFIED BY:  BILL BANDHAUER               |LAST UPDATE DATE:  01/05/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANNE BOLAND          R2      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE RESCUED SEA TURTLE                                  |
|                                                                              |
| EN #37902 started the biennial report period.                                |
|                                                                              |
| On January 1, 2002 at 0919, a rescued sea turtle was identified as a green   |
| sea turtle.  This is the 62nd rescue of a live sea turtle at Crystal River   |
| Unit 3 (CR-3) in this biennial period. Notification to the National Marine   |
| Fisheries Service and the Florida Fish and Wildlife Conservation Commission. |
|                                                                              |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| * * *  UPDATE ON 1/05/02 @ 1002 BY RAWLS TO GOULD  * * *                     |
|                                                                              |
| On January 5, 2002, at 0720, a rescued sea turtle was identified as a        |
| Loggerhead Sea Turtle. This is the 63rd rescue of a live sea turtle at       |
| Crystal River Unit 3 (CR3) in this biennial period.  This is reportable as a |
| 4-hour report under 10 CFR 50.72(b)(2)(xi) as this event is related to the   |
| protection of the environment for which a notification to other government   |
| agencies (National Marine Fisheries Service and Florida Fish and Wildlife    |
| Conservation Commission) has been or will be made.                           |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 2 RDO (Decker) was notified.                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38607       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 01/02/2002|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 21:34[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        01/02/2002|
+------------------------------------------------+EVENT TIME:        12:30[CST]|
| NRC NOTIFIED BY:  JAMES GILMORE                |LAST UPDATE DATE:  01/04/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BLAIR SPITZBERG      R4      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS)                               |
|                                                                              |
| At 1230CST SPDS was lost for reasons unknown.  Troubleshooting is currently  |
| in progress.  The licensee informed the NRC Resident Inspector.              |
|                                                                              |
| * * * Update on 01/04/02 at 1118EST by Rick Hubbard taken by S. SANDIN * *   |
| *                                                                            |
|                                                                              |
| SPDS was restored to service at 2229CST on 01/03/02.  R4DO (B. Spitzberg)    |
| notified. The licensee will inform the NRC Resident Inspector.               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38608       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 01/04/2002|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 16:12[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/05/2001|
+------------------------------------------------+EVENT TIME:        02:47[CST]|
| NRC NOTIFIED BY:  COY BLAIR                    |LAST UPDATE DATE:  01/04/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BLAIR SPITZBERG      R4      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| GROUP SIX ISOLATION  (60-Day Report)                                         |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Event Date:  5 Nov 2001"                                                    |
|                                                                              |
| "Event Time:  0247 CST"                                                      |
|                                                                              |
| "Description:"                                                               |
|                                                                              |
| "a. This telephone report is being made under 10CFR50.73(a)(2)(iv)(A)."      |
|                                                                              |
| "While performing installation work inside an energized isolation relay      |
| cabinet in the cable spreading room, a                                       |
| wire was accidentally grounded and the power supply fuse blew causing [an]   |
| inadvertent Group Six isolation."                                            |
|                                                                              |
| "b.  A Group Six isolation actuation was received consisting of the          |
| following systems[:]                                                         |
|                                                                              |
| *  Isolation of Primary Containment Vent and Purge system[,]                 |
| *  Tripped Reactor Building Ventilation Fans[,]                              |
| *  Isolation of Reactor Building Ventilation system[,]                       |
| *  Isolation of Recirculation MG Set Ventilation system[,]                   |
| *  Started Standby Gas Treatment system[, and]                               |
| *  Open Reactor Equipment Cooling system Critical Loop Isolation Valves[.]"  |
|                                                                              |
| "c.  The train actuations were [partial.  The] position of seven ventilation |
| system valves associated with Reactor                                        |
| Building Ventilation and Recirculation MG Set Ventilation were not verified  |
| due to a loss of position indication                                         |
| resulting from the blown fuse.  Primary and Secondary Containment were not   |
| required for the plant conditions."                                          |
|                                                                              |
| "d.  All systems operated as expected for a loss of power event."            |
|                                                                              |
| "The following also occurred due to the loss of electrical power[:]          |
|                                                                              |
| *  Division two valves associated with a Group Two isolation of the Drywell  |
| Ventilation Radiation Monitoring                                             |
| sample supply and return failed closed due to the loss of electrical power.  |
| There was no Group Two                                                       |
| actuation signal."                                                           |
|                                                                              |
| "These are expected actions for the loss of power event that occurred."      |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38609       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 01/05/2002|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 23:33[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/05/2002|
+------------------------------------------------+EVENT TIME:        17:50[CST]|
| NRC NOTIFIED BY:  WAYNE IRVIN                  |LAST UPDATE DATE:  01/05/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GARY SHEAR           R3      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT PROPANE TANKS ON SITE EXCEEDED THE VOLUME ASSUMED IN
THE      |
| CONTROL ROOM HABITABILITY TOXIC GAS ANALYSIS                                 |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Propane tanks on site exceeded the volume assumed in the toxic gas analysis |
| for control room habitability.  The analysis assumes 1,000 gallons were      |
| available for release.  Instead, there were two locations were two           |
| 1,000-gallon tanks were available for release (filled with propane on        |
| January 4th and then emptied on January 4th).  Upon determination that the   |
| 1,000-gallon limit was exceeded, the control room outside air intake dampers |
| were closed and remained closed until the tanks were emptied.  Reanalysis    |
| (completed today) assuming a release of 2,000 gallons results in the         |
| calculated concentration of propane in the control room exceeding the        |
| acceptance criteria."                                                        |
|                                                                              |
| The licensee stated that there was nothing unusual or misunderstood and that |
| all systems functioned as required.                                          |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38610       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 01/06/2002|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 08:43[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        01/06/2002|
+------------------------------------------------+EVENT TIME:        05:15[CST]|
| NRC NOTIFIED BY:  HUBBARD                      |LAST UPDATE DATE:  01/06/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BLAIR SPITZBERG      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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE                              |
|                                                                              |
| At 1347 on 1/4/2002, the "A" emergency diesel generator (EDG) was declared   |
| inoperable due to tube degradation identified in the lube oil, intercooler   |
| and jacket water heat exchangers.  Technical Specification 3.8.1 was         |
| entered, the affected heat exchanger tubes were plugged and the "A" EDG was  |
| restored to operable status at 1134 @ 1/5/2002.                              |
|                                                                              |
| At 1301 on 1/5/2002, the "B" EDG was taken out of service to perform         |
| inspections of its lube oil, intercooler and jacket water heat exchangers.   |
| Inspection of the heat exchanger tubes and analysis of the inspection data   |
| found similar results, subsequently resulting in the need to plug heat       |
| exchanger tubes to restore the "B" EDG to operable status.                   |
|                                                                              |
| Based upon the similarity and extent of the tube degradation in both the "A" |
| and "B" EDG heat exchangers, prior to implanting the tube plugging           |
| corrective action, the possibility exists that the degradation of the EDG    |
| heat exchangers' tubes could have prevented the fulfillment of the safety    |
| function of the onsite standby class 1E power source following a design      |
| basis earthquake.                                                            |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| * * * UPDATE ON 01/06/02 AT 1927EST BY HUBBARD TAKEN BY MACKINNON * * *      |
|                                                                              |
| "B" EDG was restored to operable status.  R4DO (B. Spitzberg) notified.      |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38611       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 01/06/2002|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 21:42[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/06/2002|
+------------------------------------------------+EVENT TIME:        14:10[EST]|
| NRC NOTIFIED BY:  PARKER                       |LAST UPDATE DATE:  01/06/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     R1      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE           
|
|                                                                              |
| During the performance of the quarterly valve surveillance test for the HPCI |
| system, a testable check valve, 1FD-V032, related to the HPCI Barometric     |
| Condenser Discharge Line, failed.  This failure rendered the HPCI system     |
| inoperable at 1410 EST on 01/06/02. The licensee entered an active 14 day    |
| Limiting Condition of Operation that expires on 01/20/02 at 1410 EST.  All   |
| other safety systems are operable.  Current plans to return plant to normal  |
| configuration include the development of corrective maintenance work         |
| package.                                                                     |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+