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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  



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|Power Reactor                                    |Event Number:   39564       |

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| 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      |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| 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.                        |

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|Power Reactor                                    |Event Number:   39566       |

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| 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.                                              |

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+------------------------------------------------------------------------------+

|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.                                |

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