United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2003 > June 6

Event Notification Report for June 6, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           06/05/2003 - 06/06/2003



                              ** EVENT NUMBERS **



39894  39903  39905  39907  



!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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

|Power Reactor                                    |Event Number:   39894       |

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

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

| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 05/30/2003|

|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 16:54[EDT]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/30/2003|

+------------------------------------------------+EVENT TIME:        08:30[EDT]|

| NRC NOTIFIED BY:  KEN ROBINSON                 |LAST UPDATE DATE:  06/05/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |LAWRENCE DOERFLEIN   R1      |

|10 CFR SECTION:                                 |                             |

|DDDD 73.71(b)(1)         SAFEGUARDS REPORTS     |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|1     N          Y       99       Power Operation  |99       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| SECURITY GUARD POSTED WITHOUT PROPER EQUIPMENT                               |

|                                                                              |

| A plant security officer was stationed at a security post without all        |

| equipment required to properly man that post. Immediate compensatory         |

| measures were taken upon discovery. The licensee notified the NRC Resident   |

| Inspector. Refer to the Headquarters Operations Officer Log for additional   |

| details.                                                                     |

|                                                                              |

| * * * UPDATE AT 1220EDT ON 6/5/03 FROM ANDREW WISNIEWSKI TO S. SANDIN        |

|                                                                              |

| The licensee upon further review concluded that the incident was logable and |

| is, therefore,  retracting this report.  The licensee informed the NRC       |

| Resident Inspector.  Notified R1DO(Linville).  Contact the Headquarters      |

| Operations Officer for details.                                              |

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



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

|Power Reactor                                    |Event Number:   39903       |

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

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

| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 06/04/2003|

|    UNIT:  [1] [2] [3]               STATE:  SC |NOTIFICATION TIME: 19:03[EDT]|

|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        06/04/2003|

+------------------------------------------------+EVENT TIME:        11:15[EDT]|

| NRC NOTIFIED BY:  RANDY TODD                   |LAST UPDATE DATE:  06/05/2003|

|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |KERRY LANDIS         R2      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|1     N          Y       100      Power Operation  |100      Power Operation  |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|3     N          N       0                         |0                         |

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

                                   EVENT TEXT                                   

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

| APPENDIX R  ISSUE                                                            |

|                                                                              |

| During an Appendix R design basis review, an Engineer noted that cables      |

| associated with normal operation of components used for one train (Primary   |

| Isolation Valves) of Appendix R mitigation were routed through an adjacent   |

| fire zone associated with the other train of Appendix R mitigation.  During  |

| an Appendix R event, control of the affected components is transferred to    |

| the Standby Shutdown Facility, which electrically isolates the subject       |

| cables.                                                                      |

|                                                                              |

| However, the area containing the subject cables does not have fire detection |

| equipment.  The Engineer noted that if a fire occurred and damaged the       |

| cables, it would be theoretically possible for a "smart short" to result in  |

| damage to equipment before action could be taken to transfer control to the  |

| Standby Shutdown Facility.                                                   |

|                                                                              |

| Initial Safety Significance:                                                 |

|                                                                              |

| This condition is similar to an example given in NUREG 1022, Section 3.2.4   |

| (fire barrier missing such that the required degree of separation for        |

| redundant safe shutdown trains is lacking).                                  |

|                                                                              |

| In order to result in a loss of safety function, the postulated fire would   |

| have to damage the cable, result in a smart spurious actuation of a          |

| component, damage that component such that it became inoperable (such as by  |

| burning out the motor of a valve), then also spread within the fire zone to  |

| damage the redundant component (for example by burning the power cable or    |

| motor control center).                                                       |

|                                                                              |

| The Oconee license basis is no spurious circuit operations for 10 minutes.   |

| Cable testing sponsored by the NRC, NEI, and EPRI for fire exposure has      |

| demonstrated that armored type cable construction used in this application   |

| is more rugged than other designs and that internal cable failure times      |

| usually extend beyond 30 minutes.                                            |

|                                                                              |

| The area containing the cables is a high traffic area for both personnel and |

| material - including low quantities of transient combustibles, but has no    |

| appreciable fixed fire loads.  Thus the probability of a fire of sufficient  |

| energy to damage the cable is low.  Pending a PRA analysis, it appears       |

| reasonable to credit prompt discovery of a fire and initiation of action to  |

| suppress the fire and/or transfer of control to the Standby Shutdown         |

| Facility prior to cable damage.  Therefore the overall risk impact of this   |

| event is currently considered low.                                           |

|                                                                              |

| Corrective Action:                                                           |

|                                                                              |

| The SSF has been declared inoperable pending establishment of a fire watch.  |

|                                                                              |

| The NRC Resident Inspector will be informed of this event by the licensee.   |

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



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

|Power Reactor                                    |Event Number:   39905       |

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

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

| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/05/2003|

|    UNIT:  [2] [3] []                STATE:  NY |NOTIFICATION TIME: 16:44[EDT]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/05/2003|

+------------------------------------------------+EVENT TIME:        15:45[EDT]|

| NRC NOTIFIED BY:  BOB HURON                    |LAST UPDATE DATE:  06/05/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JAMES LINVILLE       R1      |

|10 CFR SECTION:                                 |DAVID MATTHEWS       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 2 OFFSITE EMERGENCY NOTIFICATION SIRENS AT INDIAN POINT              |

|                                                                              |

| On 06/05/03 at 1644 EDT the licensee reported that 2 of 16 emergency         |

| notification sirens located in Orange County failed on 06/05/03 at 1545 EDT  |

| due to a loss of power. An investigation is underway to determine the cause  |

| and restore power to the affected sirens.                                    |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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



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

|Power Reactor                                    |Event Number:   39907       |

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

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

| FACILITY: MAINE YANKEE             REGION:  1  |NOTIFICATION DATE: 06/05/2003|

|    UNIT:  [1] [] []                 STATE:  ME |NOTIFICATION TIME: 17:25[EDT]|

|   RXTYPE: [1] CE                               |EVENT DATE:        06/05/2003|

+------------------------------------------------+EVENT TIME:        16:47[EDT]|

| NRC NOTIFIED BY:  TERRY VOGEL                  |LAST UPDATE DATE:  06/05/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JAMES LINVILLE       R1      |

|10 CFR SECTION:                                 |                             |

|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          N       0        Decommissioned   |0        Decommissioned   |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| OFFSITE NOTIFICATION TO STATE AGENCIES INVOLVING UNSCHEDULED RELEASE         |

|                                                                              |

| The following information was provided by the licensee via fax:              |

|                                                                              |

| "Notified Maine Emergency Management Agency of unscheduled release that      |

| occurred on Monday June 2, 2003.  Notified Department of Human Services of   |

| same.                                                                        |

|                                                                              |

| "Maine Yankee released 3E-8 curies of liquid. 3E-8 curies of this release    |

| exceeded the value projected for this period and is, therefore, classified   |

| as unscheduled.  The total liquid release resulted in an exposure value of   |

| 1E-8 millirem.                                                               |

|                                                                              |

| "This unscheduled release resulted from low levels of Cs-137 exiting the     |

| restricted area via a storm drain, and occurred throughout the 24-hr time    |

| period from 6-2-3."                                                          |

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