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
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|Power Reactor |Event Number: 39551 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 39552 |
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| 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
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| 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. |
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|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. |
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|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
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| 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. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021