Event Notification Report for February 23, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/22/2001 - 02/23/2001
** EVENT NUMBERS **
37771 37772
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|Power Reactor |Event Number: 37771 |
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| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 02/22/2001|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 16:28[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 02/21/2001|
+------------------------------------------------+EVENT TIME: 18:45[CST]|
| NRC NOTIFIED BY: HENSON |LAST UPDATE DATE: 02/22/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|10 CFR SECTION: | |
|*PRE 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 |
| | |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION MADE TO MISSOURI PUBLIC SERVICE COMMISSION |
| |
| An onsite apprentice welder injured his left hand. Onsite Medical Emergency |
| Team evaluated the injury and had the individual transported offsite to the |
| local hospital. The Missouri Public Service Commission was notified of this |
| incident by the licensee. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 37772 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 02/22/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 21:34[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 02/22/2001|
+------------------------------------------------+EVENT TIME: 18:30[CST]|
| NRC NOTIFIED BY: B. WELLER |LAST UPDATE DATE: 02/22/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK RING R3 |
|10 CFR SECTION: | |
|*INB 50.72(b)(3)(v)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| "EVEN" TRAIN CORE SPRAY, RHR OR RHRSW PUMPS OPERATION FROM THE ALTERNATE |
| SHUTDOWN SYSTEM COULD BE LOST DUE TO A POSTULATED HOT SHORT. |
| |
| An Alternate Shutdown System design deficiency resulting in a vulnerability |
| to a single hot short during a Control Room Cable Spreading Room fire has |
| been identified. The effect of the postulated hot short would be to actuate |
| the Bus 16 load shed logic while the bus is powered from the emergency |
| diesel generator. This could result in the inability to operate the even |
| train Core Spray, Residual Heat Removal (RHR) or RHR Service Water pumps. |
| No means are in place to circumvent the postulated hot short. A one hour |
| fire watch patrol in the cable spreading room and control room has been |
| established with Alternate Shutdown System inoperable. All other Emergency |
| Core Cooling Systems are fully operable. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
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