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Event Notification Report for May 15, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           05/14/2003 - 05/15/2003



                              ** EVENT NUMBERS **



39844  39845  39846  39847  39848  39849  



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|Power Reactor                                    |Event Number:   39844       |

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| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 05/14/2003|

|    UNIT:  [] [3] []                 STATE:  PA |NOTIFICATION TIME: 11:43[EDT]|

|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        05/14/2003|

+------------------------------------------------+EVENT TIME:        04:10[EDT]|

| NRC NOTIFIED BY:  JAMES VASH                   |LAST UPDATE DATE:  05/14/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |KENNETH JENISON      R1      |

|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   |

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

|                                                   |                          |

|3     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| APPENDIX "R" ISSUE AT PEACH BOTTOM 3                                         |

|                                                                              |

| "On May 14, 2003, at approximately 0410, the shift supervisor determined     |

| that the Alternate Shutdown Panel on Unit 3 was not operable following       |

| discovery of a de-energized power supply. The panel provides the capability  |

| to maintain a safe shutdown path for a fire in the cable spreading room,     |

| main control room or main control room fan room. Therefore, operators would  |

| have been prevented from implementing required actions for a fire in those   |

| areas. The apparent cause of the loss of power was a broken wire, which was  |

| discovered during routine testing of the panel.                              |

|                                                                              |

| "Power was restored to the Alternate Shutdown Panel at approximately 1030 on |

| May 14, 2003 and further investigation is in progress to determine the cause |

| of the broken wire and full extent and effect of the de-energization of the  |

| panel."                                                                      |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

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|Hospital                                         |Event Number:   39845       |

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| REP ORG:  UNIVERSITY WISCONSIN-MADISON         |NOTIFICATION DATE: 05/14/2003|

|LICENSEE:  UNIVERSITY WISCONSIN-MADISON         |NOTIFICATION TIME: 12:35[EDT]|

|    CITY:  MADISON                  REGION:  3  |EVENT DATE:        05/13/2003|

|  COUNTY:                            STATE:  WI |EVENT TIME:        14:00[CDT]|

|LICENSE#:  4809843-18            AGREEMENT:  N  |LAST UPDATE DATE:  05/14/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |SONIA BURGESS        R3      |

|                                                |JOHN HICKEY          NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  RONALD BRESELLS              |                             |

|  HQ OPS OFFICER:  RICH LAURA                   |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|LDIF 35.3045(a)(1)       DOSE <> PRESCRIBED DOSA|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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| MEDICAL EVENT AT UNIVERSITY WISCONSIN-MADISON                                |

|                                                                              |

| A significant under-exposure occurred on a patient undergoing therapy for    |

| liver cancer. The source was an SIR-SPHERE using .058 curies of Y-90         |

| isotope. The Y-90 isotope was in semi-liquid form.  The prescribed dose was  |

| 58 milli-curies and the patient was delivered only 2 milli-curies. The       |

| vendor of the machine has been contacted and will repair the equipment. The  |

| hospital speculated that the delivery tube may have had air leaks resulting  |

| in the source not being fully inserted. The patient has been rescheduled for |

| the therapy on May 28, 2003.                                                 |

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|Power Reactor                                    |Event Number:   39846       |

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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 05/14/2003|

|    UNIT:  [2] [3] []                STATE:  NY |NOTIFICATION TIME: 15:46[EDT]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        05/14/2003|

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

| NRC NOTIFIED BY:  JOHN BAKER                   |LAST UPDATE DATE:  05/14/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |KENNETH JENISON      R1      |

|10 CFR SECTION:                                 |MICHAEL CASE         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       99       Power Operation  |99       Power Operation  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| LOSS OF SIRENS                                                               |

|                                                                              |

| "Indian Point Energy Center (IPEC) Units 2 and 3 are making an eight-hour    |

| non-emergency notification in accordance with 10CFR50.72(b)(3)(xiii).        |

|                                                                              |

| "On May 14, 2003 at 1035 [EDT], Rockland County notified Emergency Planning  |

| (EP) that while attempting to perform a 'Cancel Test' of the counties sirens |

| a communication failure was recorded on all Rockland County sirens. EP       |

| performed a review of the status of the system and determined that a         |

| communication loss was experienced that prevented transmittal of             |

| instructions to all sirens in the four counties. Communication between the   |

| Indian Point Energy Center Emergency Operations Facility (EOF) and the 154   |

| sirens was re-established as of 1251 [EDT].  Personnel will continuously man |

| the EOF to initiate sirens if needed, until control can be re-established    |

| from the affected counties. Route alerting was available during the loss of  |

| sirens.                                                                      |

|                                                                              |

| "The NRC resident inspector, County and State were notified of this event."  |

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

|Power Reactor                                    |Event Number:   39847       |

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

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

| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 05/14/2003|

|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 17:22[EDT]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        05/14/2003|

+------------------------------------------------+EVENT TIME:        09:45[EDT]|

| NRC NOTIFIED BY:  PETE GARDNER                 |LAST UPDATE DATE:  05/14/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |KENNETH JENISON      R1      |

|10 CFR SECTION:                                 |                             |

|HFIT 26.73               FITNESS FOR DUTY       |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|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  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| FITNESS FOR DUTY                                                             |

|                                                                              |

| A licensed employee was determined to be under the influence of alcohol      |

| during a random drug test.  The employee's access to the plant has been      |

| removed.  Contact the HOO for additional details.                            |

|                                                                              |

| The licensee informed the NRC Resident Inspector.                            |

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

|Power Reactor                                    |Event Number:   39848       |

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

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

| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 05/14/2003|

|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 18:44[EDT]|

|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        05/14/2003|

+------------------------------------------------+EVENT TIME:        09:45[EDT]|

| NRC NOTIFIED BY:  RICK LLEWELLYN               |LAST UPDATE DATE:  05/14/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |KENNETH JENISON      R1      |

|10 CFR SECTION:                                 |                             |

|HFIT 26.73               FITNESS FOR DUTY       |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|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                                   

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

| FITNESS FOR DUTY                                                             |

|                                                                              |

| A licensed employee was determined to be under the influence of alcohol      |

| during a random drug test given at the Limerick Generating Station.          |

| Employee was dual-licensed at both Limerick and Peach Bottom. (Refer to      |

| Event Notification #39847).  The employee's access to the plant has been     |

| removed.  Contact the Headquarters Operations Officer for additional         |

| details.                                                                     |

|                                                                              |

| The NRC Resident Inspector has been notified by the licensee.                |

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



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|Power Reactor                                    |Event Number:   39849       |

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

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

| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 05/15/2003|

|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 05:27[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/15/2003|

+------------------------------------------------+EVENT TIME:        02:52[CDT]|

| NRC NOTIFIED BY:  HALL                         |LAST UPDATE DATE:  05/15/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JOHNSON      R4      |

|10 CFR SECTION:                                 |MICHAEL CASE         NRR     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|RICHARD WESSMAN      IRO     |

|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     A/R        Y       100      Power Operation  |0        Hot Standby      |

|2     A/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| REACTOR TRIP FROM 100% POWER ON BOTH UNITS DUE TO TURBINE TRIP ON BOTH       |

| UNITS                                                                        |

|                                                                              |

| The licensee reported that a loss of power on the 345KV grid caused a        |

| turbine trip on both units which resulted in a reactor trip from 100% on     |

| both units.  All rods fully inserted and no ECCS was actuated.  Both units   |

| are currently at Mode 3 in natural circulation and stable.  The auxiliary    |

| feed water systems started on both units to maintain steam generator levels. |

| The reactor coolant temperature is being controlled by using the steam       |

| generator atmospheric relief valves.  Since the safety systems were powered  |

| by an alternate offsite power supply, the 4 emergency diesels did not auto   |

| start, but they are operable.  The licensee is investigating why they lost   |

| the 345KV grid.                                                              |

|                                                                              |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

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