Event Notification Report for June 6, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/05/2001 - 06/06/2001
** EVENT NUMBERS **
37997 38052 38053
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37997 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 05/16/2001|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 18:26[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/16/2001|
+------------------------------------------------+EVENT TIME: 11:11[EDT]|
| NRC NOTIFIED BY: BRAD BROWN |LAST UPDATE DATE: 06/05/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLES R. OGLE R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| DISCOVERY THAT THE CONTROL ROOM HABITABILITY SYSTEM MAY NOT MEET DESIGN |
| REQUIREMENTS UNDER CERTAIN CONDITIONS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "The control room habitability system may not meet design requirements under |
| certain conditions. Specifically, any design accident where the control |
| room bottled air pressurization system actuates and the exhaust fan of the |
| cable vault and tunnel area trips with the supply fan to the cable vault and |
| tunnel continuing to run, the minimum delta pressure between these areas may |
| not be maintained." |
| |
| "The control room bottled air systems of both Unit 1 and 2 have been |
| declared inoperable, and a 7-day [technical specification action statement |
| has] been entered." |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| * * * RETRACTED AT 1141 EDT ON 6/6/01 BY JAMES CROSSMAN TO FANGIE JONES * * |
| * |
| |
| After subsequent engineering evaluation, the licensee has determined that |
| this event was not reportable and is retracting the event notification. The |
| evaluation concluded that the effect of a failure of a non-safety related |
| component on the control room envelope and bottle air system is not required |
| during a design basis accident. Therefore, the proposed (not actual) |
| failure assumptions are not considered reasonable and there is no need to |
| report this condition. |
| |
| The licensee notified the NRC Resident Inspector. The R2DO (Ken Barr) was |
| notified. |
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|Power Reactor |Event Number: 38052 |
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| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 06/05/2001|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 04:59[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 06/05/2001|
+------------------------------------------------+EVENT TIME: 00:00[CDT]|
| NRC NOTIFIED BY: BRADLY McMAHON |LAST UPDATE DATE: 06/05/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|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 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LOSS OF PROCESS COMPUTER WITH LINK TO SAFETY PARAMETERS DISPLAY SYSTEM |
| |
| The plant process computer system failed. This system provides a link to |
| the Safety Parameter Display System (SPDS). Immediate actions were taken to |
| restore the computer and SPDS to no avail. The plant computer group |
| representative has been called in to address the computer problem. Work |
| continues to try and restore the computer to operation. Also, the |
| availability of the Emergency Response Data System (ERDS) availability is |
| questionable. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 38053 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/05/2001|
| UNIT: [1] [] [] STATE: FL |NOTIFICATION TIME: 13:24[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 06/05/2001|
+------------------------------------------------+EVENT TIME: 10:48[EDT]|
| NRC NOTIFIED BY: C. MARPLE |LAST UPDATE DATE: 06/05/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN BONSER R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNEXPECTED TRIP OF THE "1A2" REACTOR COOLANT PUMP CAUSED A TURBINE |
| TRIP/REACTOR TRIP. |
| |
| On 06/05/01 at 1048ET St. Lucie Unit 1 experienced an unexpected trip of the |
| "1A2" Reactor Coolant Pump. This was immediately followed by an automatic |
| reactor trip from the Reactor Protection System on reactor coolant low flow |
| and subsequent turbine trip. All rods fully inserted into the core. |
| Approximately one minute later the "1B" Main Feedwater pump tripped and then |
| the Auxiliary Feedwater System actuated, "B" Electric Driven Auxiliary |
| Feedwater Pump and the Turbine Driven Auxiliary Feedwater Pump, to the "1B" |
| Steam Generator. The Reactor Coolant System is stable in Mode 3, Hot |
| Standby, with the secondary steaming via the steam bypass control system and |
| feedwater from the "1A" Main Feedwater Pump. The causes of the Reactor |
| Coolant Pump trip and the Main Feedwater pump trip are currently under |
| investigation. All Emergency Core Cooling Systems and the Emergency Diesel |
| Generators are fully operable if needed. |
| |
| Steam generator safety valves opened/closed. No leaking steam generator |
| tubes. |
| |
| "1A" Component Cooling Water Heat Exchanger and the "1A" Reactor Vessel |
| Level Monitoring System were inoperable during the reactor trip. |
| |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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