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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|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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| *** NOT FOR PUBLIC DISTRIBUTION *** |
|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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021