Event Notification Report for January 3, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/02/2002 - 01/03/2002
** EVENT NUMBERS **
38604 38605 38606 38607
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|Power Reactor |Event Number: 38604 |
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+------------------------------------------------------------------------------+
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| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 01/02/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 04:56[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 01/02/2002|
+------------------------------------------------+EVENT TIME: 03:05[EST]|
| NRC NOTIFIED BY: SCOTT SAUNDERS |LAST UPDATE DATE: 01/02/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE BOLAND R2 |
|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 7 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP DUE TO DECREASING STEAM GENERATOR WATER LEVEL.
|
| |
| During a plant start-up at 7% reactor power, feedwater oscillations occurred |
| on all three steam generators. At 0215 on 01/02/02 the main feedwater |
| regulator bypass valves were placed in manual control to stabilize level. |
| The bypass valves were then returned to automatic control at 0245 on |
| 01/02/02, and the oscillations continued within the normal operating band of |
| 52-62%. At 0300 0n 01/02/02. The Control Operator noted lowering level on |
| the "C" steam generator at approximately 55% with indication that the "C" |
| main feedwater regulator bypass valve was shut. The operator placed the "C" |
| bypass valve in manual control and attempted to open the valve with no |
| response noted in valve position indication. At 30% indicated level in the |
| "C" steam generator and a lowering trend, the Unit Shift Control Operator |
| ordered a manual reactor trip prior to receipt of a steam generator low |
| water level trip signal at 25%. All safety systems functioned as expected. |
| Both Motor Driven Auxiliary Feedwater Pumps automatically actuated on the |
| subsequent 'C" steam generator low water level signal. All rods fully |
| inserted into the core and the electrical grid is stable. An investigation |
| into what caused this event is in progress. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 38605 |
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| FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 01/02/2002|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 09:48[EST]|
| RXTYPE: [1] B&W-R-LP |EVENT DATE: 01/02/2002|
+------------------------------------------------+EVENT TIME: 01:50[EST]|
| NRC NOTIFIED BY: MYERS |LAST UPDATE DATE: 01/02/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GARY SHEAR 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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) IS OUT OF SERVICE |
| |
| The SPDS has not been functioning since 01:50. It has been operable for |
| about one hour, but they are still monitoring it before they determine it to |
| be completely operable. |
| |
| The NRC Resident Inspector will be notified. |
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|Fuel Cycle Facility |Event Number: 38606 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE:
01/02/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:47[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/02/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:52[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/02/2002|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KEITH WILLIAMSON | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 4-HOUR REPORT DUE TO EPA NOTIFICATION REGARDING AN OPACITY VIOLATION
|
| |
| The #3 High Pressure Blower on Boiler #3 tripped due to a suspected |
| equipment malfunction causing a pollutant discharge exceeding the 20% |
| opacity limit in any one hour period specified by EPA to occur between 0915 |
| and 0921EST. Operations notified the NRC Resident Inspector and the Ohio |
| Environmental Protection Agency (OEPA) of the violation. |
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|Power Reactor |Event Number: 38607 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 01/02/2002|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 21:34[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 01/02/2002|
+------------------------------------------------+EVENT TIME: 12:30[CST]|
| NRC NOTIFIED BY: JAMES GILMORE |LAST UPDATE DATE: 01/02/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS) |
| |
| At 1230CST SPDS was lost for reasons unknown. Troubleshooting is currently |
| in progress. The licensee informed the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021