Event Notification Report for January 14, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/13/2003 - 01/14/2003
** EVENT NUMBERS **
39505 39506 39507
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|Power Reactor |Event Number: 39505 |
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| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/13/2003|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 02:48[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/12/2003|
+------------------------------------------------+EVENT TIME: 23:04[EST]|
| NRC NOTIFIED BY: RITA BRADDICK |LAST UPDATE DATE: 01/13/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 |
|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 |
| | |
| | |
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EVENT TEXT
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| OPEN DUCTWORK ACCESS PANEL PREVENTED MAINTAINING CONTROL ROOM POSITIVE |
| PRESSURE |
| |
| "On January 12, 2003 at 2304, control room pressure was observed to be |
| negative. At the time the "A" Control Room Emergency Filtration (CREF) |
| system was tagged out for scheduled maintenance. The event was initiated |
| when technicians opened an access panel on the "A" CREF control room air |
| supply duct within the control room boundary to repair a gasket. This |
| resulted in both "A" and "B" trains of CREF unable to perform its design |
| safety function: specifically, maintaining the control room at a 1/8 inch |
| water gauge positive pressure relative to adjacent areas. Without assurance |
| of CREF system providing positive pressure in the control room, mitigating |
| the consequences of an accident could have been prevented. Upon discovering |
| the cause, technicians were ordered to close the access panel. Control room |
| pressure promptly returned to a normal, positive value. Total time at |
| negative pressure was ten minutes. No unexpected response was experienced. |
| In addition to the "A" CREF train, the "A" Hydrogen/Oxygen analyzer was |
| inoperable at the time of the event." |
| |
| The licensee has notified the NRC resident inspector. |
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|Power Reactor |Event Number: 39506 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/13/2003|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 08:47[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/13/2003|
+------------------------------------------------+EVENT TIME: 06:18[EST]|
| NRC NOTIFIED BY: ANDREW BARTLIK |LAST UPDATE DATE: 01/13/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD BARKLEY R1 |
|10 CFR SECTION: |JOHN HANNON NRR |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSER CIRCULATING WATER PUMP |
| |
| At 0618 EST the #35 Circulating Water Pump tripped. The other circulating |
| water pump supplying the same condenser section was out of service for |
| maintenance. The resulting loss of all circulating water to one condenser |
| section produced a high differential pressure between sections. The reactor |
| was manually tripped in accordance with plant procedures. All controlled |
| rods fully inserted. The Auxiliary Feedwater Pump automatically started as |
| expected. During the transient, the #32 Reactor Coolant Pump tripped due to |
| an unknown cause and is being investigated. Additionally, the # R14 Plant |
| Vent Gas radiation monitor went into alarm and then immediately returned to |
| normal, however the redundant monitor did not show any increase in |
| radiation. Additionally, the #32 Source Range Detector did not come on |
| scale on the reactor trip, however the redundant detector functioned |
| normally. The electrical system responded normally. There were no releases |
| associated with this event. The cause of the circulating water pump trip is |
| under investigation. |
| |
| The licensee has notified the NRC resident inspector. |
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|Power Reactor |Event Number: 39507 |
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| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 01/14/2003|
| UNIT: [1] [] [] STATE: VA |NOTIFICATION TIME: 04:18[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/14/2003|
+------------------------------------------------+EVENT TIME: 01:37[EST]|
| NRC NOTIFIED BY: ALISON MACKELLAR |LAST UPDATE DATE: 01/14/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROBERT HAAG 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 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO HIGH REACTOR COOLANT PUMP SHAFT VIBRATION |
| |
| "At 0137 hours, with Surry Power Station Unit 1 at 100% reactor power, a |
| manual reactor trip was initiated due to elevated shaft vibrations (alert |
| and danger) on "C" Reactor Coolant Pump. |
| |
| IRPI indication for one control rod indicated 25 steps following the trip. |
| Borated as necessary to ensure adequate shutdown margin. All other control |
| rods fully inserted into the core as designed. The IRPI indication for this |
| rod is trending down at this time. The shutdown margin for Unit 1 was |
| determined to be satisfactory. Auxiliary feedwater automatically initiated |
| as designed on low low steam generator level following the trip. Primary |
| RCS temperature decreased to approximately 541 degrees following the reactor |
| trip and was stabilized at 547 degrees. |
| |
| "No primary safety or power operated relief valves were actuated during the |
| event. As a result of the loss of turbine load, the secondary power operated |
| relief valves actuated during the transient. No indication of primary to |
| secondary leakage exists, therefore no adverse radiological consequences |
| resulted from this event. |
| |
| "All electrical busses transferred properly following the trip. #1 EDG was |
| T/O [tagged out] prior to unit trip. All other emergency diesel generators |
| are operable. There were no radiation releases due to this event, nor were |
| there any personnel injuries or contamination events. The cause of the |
| event is being investigated. |
| |
| "Unit 1 is currently at Hot Shutdown with RCS temperature being maintained |
| at approximately 547 degrees. Unit 2 was not affected by this event and |
| remains stable at 100% power operations. This event Is being reported In |
| accordance with 10CFR50.72(b)(2)(iv) and I0CFR50.72(b)(3)(iv)." |
| |
| 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