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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+------------------------------------------------------------------------------+
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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
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| 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. |
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+------------------------------------------------------------------------------+
|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. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38607 |
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| 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. |
+------------------------------------------------------------------------------+
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