Event Notification Report for May 10, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/09/2001 - 05/10/2001
** EVENT NUMBERS **
37976 37977 37978 37979
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|Power Reactor |Event Number: 37976 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 05/09/2001|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 14:45[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 05/09/2001|
+------------------------------------------------+EVENT TIME: 14:07[EDT]|
| NRC NOTIFIED BY: CRAIG MOWREY |LAST UPDATE DATE: 05/09/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES R. OGLE R2 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE COMPENSATORY ACTIONS |
| TAKEN UPON DISCOVERY. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37977 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/09/2001|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 16:23[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 05/09/2001|
+------------------------------------------------+EVENT TIME: 14:20[CDT]|
| NRC NOTIFIED BY: DAVE VANDERKAMP |LAST UPDATE DATE: 05/09/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|*UNA 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FIRE PROTECTION REQUIREMENTS NOT MET |
| |
| It has been discovered that all necessary compensatory actions for |
| inoperable fire barriers are not included in the stations operating |
| procedures for conditions when the swing 125 VDC and 250 VDC battery |
| chargers are in service supplying the 'B' DC Electrical subsystem. The |
| required degree of separation per 10CFR50 Appendix R does not exist between |
| divisions when either swing charger is connected to the 'B' DC Electrical |
| subsystem. Use of the swing chargers is not a normal lineup but has occurred |
| during the past three years. The uncompensated lack of an adequate fire |
| barrier between divisions of safe shutdown equipment is considered an |
| unanalyzed condition that significantly degrades plant safety. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37978 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 05/09/2001|
| UNIT: [] [2] [] STATE: MN |NOTIFICATION TIME: 20:37[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 05/09/2001|
+------------------------------------------------+EVENT TIME: 15:06[CDT]|
| NRC NOTIFIED BY: ED HEINEMAN |LAST UPDATE DATE: 05/09/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 |
|10 CFR SECTION: | |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |18 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN |
| |
| Initiation of a unit shutdown began at 1700 May 9, 2001, as required by T.S. |
| 3.7.B because Unit 2 Diesel Generators D5 and D6 were declared inoperable at |
| 1506. They were declared inoperable because it was determined that they may |
| not be capable of long-term operation as assumed in the plant accident |
| analyses. This determination is based on the discovery that the diesel fuel |
| and lubricating fluids in the engines may be incompatible and may damage the |
| engines based on a re-review of industry operating experience. |
| |
| The plant will go to Mode 5 and remain their until corrective actions are |
| complete. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37979 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 05/09/2001|
| UNIT: [] [2] [] STATE: MN |NOTIFICATION TIME: 21:53[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 05/09/2001|
+------------------------------------------------+EVENT TIME: 20:05[CDT]|
| NRC NOTIFIED BY: ED HEINEMAN |LAST UPDATE DATE: 05/09/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 12 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL TURBINE TRIP - AUTOMATIC REACTOR TRIP |
| |
| Initiated manual turbine trip due to condenser vacuum differential pressure |
| which resulted in an automatic reactor trip. Reactor power prior to the |
| trip was 12.5%. The cause of the high condenser vacuum differential |
| pressure is undetermined at this time. |
| |
| All control rods fully inserted, reactor coolant pumps are running. The |
| steam generators are being fed with auxiliary feed. Decay heat is being |
| removed by dumping steam with the turbine bypass atmospheric dumps. There |
| are no known S/G tube leaks. |
| |
| The licensee notified the NRC resident inspector. |
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