Event Notification Report for February 7, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/06/2003 - 02/07/2003
** EVENT NUMBERS **
39564 39566 39567 39571
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39564 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 02/06/2003|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 00:12[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/05/2003|
+------------------------------------------------+EVENT TIME: 20:58[EST]|
| NRC NOTIFIED BY: DEAN BRUCK |LAST UPDATE DATE: 02/06/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KENNETH RIEMER R3 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR WATER LEVEL |
| |
| "In accordance with 10 CFR 50.72(b)(2)(iv)(B) 'Any event or condition that |
| results in actuation of the Reactor Protection System (RPS) when the reactor |
| is critical except when the actuation results from and is part of a |
| pre-planned sequence during testing or reactor operation', DC Cook Unit 2 is |
| making a 4 hour non-emergency report. |
| |
| "On 2-5-03, at 2058, Cook Unit 2 tripped due to a failed 24 VDC control |
| group #3 power supply. This caused the feedwater regulating valve for Steam |
| Generator #3 to fail closed and the reactor tripped on Feed-flow/Steam-flow |
| mismatch coincident with low level on loop 3. All control rods inserted, the |
| turbine tripped and auxiliary feedwater pumps started as designed. The Main |
| Steam Stop Valves were manually closed during the implementation of the |
| Emergency Procedures to stop the RCS cooldown. There were no other notable |
| occurrences as a result of the trip. |
| |
| "The RCS is currently stable in Mode 3 at normal operating pressure and |
| temperature. Activities are in progress to determine the cause of the power |
| supply failure and the extent of condition." |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39566 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 02/06/2003|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 13:03[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/06/2003|
+------------------------------------------------+EVENT TIME: 09:45[EST]|
| NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 02/06/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES NOGGLE R1 |
|10 CFR SECTION: |TERRY REIS NRR |
|APRE 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE AND LOCAL AGENCIES REGARDING TRITIUM SPILL |
| |
| "Notification was made to the state of New Jersey to report a spill of |
| radioactive material, specifically, tritium at a concentration of 6.92 E-5 |
| microcuries/ml. The material is presently contained on the property of |
| Salem Generating Station and was discovered at 0945 on February 6, 2003. |
| |
| "Soil samples obtained at a depth of 20 feet from 2 monitoring wells |
| indicates the presence of tritium. The monitoring wells are adjacent to |
| Salem Unit 1 and within the protected area. We recently sampled all |
| domestic water supplies and the results were negative. There is no |
| indication of any offsite release, there is no threat to the public or |
| company employees. We cannot determine at this time if this is an existing |
| or historic condition. We are continuing with additional analysis to |
| determine the source and extent of the condition." |
| |
| The licensee informed state agencies and the NRC resident inspector and will |
| inform the local agency of LAC. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39567 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/06/2003|
| UNIT: [2] [3] [] STATE: NY |NOTIFICATION TIME: 13:23[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/05/2003|
+------------------------------------------------+EVENT TIME: 16:34[EST]|
| NRC NOTIFIED BY: RICH ALEXANDER |LAST UPDATE DATE: 02/06/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES NOGGLE R1 |
|10 CFR SECTION: |TERRY REIS NRR |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF TWO EMERGENCY SIRENS IN ORANGE COUNTY DUE TO POWER OUTAGE |
| |
| "Indian Point Energy Center (IPEC) Units 2 and 3 is making an eight-hour |
| non-emergency notification in accordance with 10CFR50.72(b)(3)(xiii). |
| |
| "On February 4, 2003, during a scheduled quarterly test of the offsite |
| emergency notification system, two (2) sirens out of a total of 16 in Orange |
| County failed to respond. These two sirens are located in Harriman State |
| Park. The cause for the failure was subsequently determined, based on |
| information provided by park rangers, to have been attributed to a loss of |
| power in the area serving the sirens. Power was fully restored to the |
| affected sirens at approximately 0500 hours on February 5, 2003 and had been |
| unavailable for approximately 17 hours. |
| |
| "The NRC resident inspector was notified of this event." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39571 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/06/2003|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 19:04[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/06/2003|
+------------------------------------------------+EVENT TIME: 12:11[EST]|
| NRC NOTIFIED BY: RICHARD ALEXANDER |LAST UPDATE DATE: 02/06/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES NOGGLE R1 |
|10 CFR SECTION: |CYNTHIA CARPENTER NRR |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION FOR CABLE SEPARATION CRITERIA AT INDIAN POINT 2 |
| |
| "At 1600 hours on February 6, 2003, IP determined that CR IP-2002.00765, |
| issued to identify that the routing of charging pump power supply and |
| control cables does not meet the cable separation criteria specified in |
| 10CFR50 App R section III.G.1, was reportable as a potentially unanalyzed |
| condition. This condition was discovered during the re-baseline of the |
| 10CFR50 Appendix R analysis. A fire in Fire Area F could potentially |
| disable all 3 charging pumps as a result of the loss of the 23 charging pump |
| alternate power feed transfer switch; loss of the 23 charging pump |
| 'alternate' power feed cable, and the alternate/normal power feed cable |
| between the transfer switch and the pump; loss of 22CHP power feed cable; |
| loss of local/remote control cable, PL2, disabling remote operation for all |
| 3 charging pump breakers; and loss of Control cables and pneumatics 22 and |
| 23 charging pumps. Fire protection impairment actions were implemented per |
| Procedure SAO-703. This condition was determined to be reportable using the |
| guidance of NUREG-1022 which cites the absence of adequate separation |
| between redundant shutdown trains to be reportable as a significant |
| degradation of plant safety. Although it is possible that this condition |
| was previously identified and dispositioned, an analysis is not readily |
| available." |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021