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Event Notification Report for December 20, 2002



                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/19/2002 - 12/20/2002

                              ** EVENT NUMBERS **

39457  39460  39461  39463  39464  

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|General Information or Other                     |Event Number:   39457       |
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 12/17/2002|
|LICENSEE:  SCHLUMBERGER                         |NOTIFICATION TIME: 18:00[EST]|
|    CITY:  DALLAS FT WORTH APT      REGION:  4  |EVENT DATE:        12/15/2002|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CST]|
|LICENSE#:  L01833                AGREEMENT:  Y  |LAST UPDATE DATE:  12/17/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA HOWELL  email  R4      |
|                                                |ROBERT PIERSON email NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS                |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PACKAGE AT DALLAS FORT WORTH (DFW) AIRPORT EXCEEDS RADIATION LIMITS BASED ON |
| LABELING                                                                     |
|                                                                              |
| "The package exceeded the package limits based on the labeling and the       |
| container. Radiation readings were about 17 mR/hr. at one meter. The limit   |
| was 10 mR/hr. at one meter. A yellow Ill and Yellow II label provided        |
| inconsistent radiation information. The package was held at a cargo bay by   |
| US Customs. The TDH/BRC responded to a call for assistance to survey the     |
| package and help determine its contents. The inspector responded on site     |
| performed a survey and notified the Licensee's RSO. The Licensee planned to  |
| send a representative to repackage and relabel the package prior to the      |
| package being released for shipment to Houston, TX. The information provided |
| is preliminary and based on telephone conversations with involved parties."  |
|                                                                              |
| The package was air cargo on an international flight being shipped from      |
| Schumberger in Singapore to Schlumberger in Houston, TX.                     |
|                                                                              |
| The Texas Department of Health, Bureau of Radiation Control has notified NRC |
| R4, US Customs, DFW, and the licensee.                                       |
|                                                                              |
| The Texas Department of Health, Bureau of Radiation Control incident number  |
| is I-7962                                                                    |
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|Power Reactor                                    |Event Number:   39460       |
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| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 12/19/2002|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 05:42[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        12/19/2002|
+------------------------------------------------+EVENT TIME:        03:59[CST]|
| NRC NOTIFIED BY:  JAMES CRABILL                |LAST UPDATE DATE:  12/19/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LINDA HOWELL         R4      |
|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 MAIN TURBINE GENERATOR TRIP                    |
|                                                                              |
| "Main Turbine Generator and Reactor trip from 100% power.  All control rods  |
| inserted.  Plant is stable in Mode 3, Hot Standby.  No release in            |
| progress."                                                                   |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector and the State of        |
| Arkansas.                                                                    |
|                                                                              |
| The Licensee indicated that no ECCS actuation occurred, the electrical grid  |
| is stable with all Emergency Diesel Generators available, and that there is  |
| no primary to secondary Steam Generator leakage.                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39461       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OK DEQ RAD MANAGEMENT                |NOTIFICATION DATE: 12/19/2002|
|LICENSEE:                                       |NOTIFICATION TIME: 10:38[EST]|
|    CITY:  Oklahoma City            REGION:  4  |EVENT DATE:        12/17/2002|
|  COUNTY:  Kingfisher                STATE:  OK |EVENT TIME:        10:00[CST]|
|LICENSE#:  OK-15794-01           AGREEMENT:  Y  |LAST UPDATE DATE:  12/19/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA HOWELL         R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MIKE BRODERICK               |                             |
|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE                               |
|                                                                              |
| At 1038 EST on 12/19/02, Oklahoma Department of Environmental Quality        |
| notified us that on 12/17/02 at 1000 CST, an Oklahoma Department of          |
| Transportation (ODOT) Troxler Moisture Density gauge was damaged in an       |
| accident.   The accident occurred when a subcontractor's water tank truck    |
| backed over an ODOT pickup truck and the gauge that was resting on the       |
| Standard Block.  The gauge was damaged, but the sealed sources were          |
| contained in shielding and were not ruptured. The gauge, S/N 27829, contains |
| an 8 millicurie Cs-137 source and a 40 millicurie Am-241/Be source. The      |
| gauge will be shipped to Troxler for repair or disposal.                     |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39463       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 12/19/2002|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 17:49[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        12/19/2002|
+------------------------------------------------+EVENT TIME:        14:30[EST]|
| NRC NOTIFIED BY:  WOODBURY                     |LAST UPDATE DATE:  12/19/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PAUL FREDRICKSON     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING(RCIC) SYSTEM OPERATION FROM THE REMOTE S/D    |
| PANEL MAY NOT BE AVAILABLE FOR SAFE SHUTDOWN OF THE UNIT.                    |
|                                                                              |
| On December 19, 2002, during an engineering review of the impact of          |
| electrical faults on the ability of systems required to safely shutdown the  |
| facility in the event of a fire, it was determined that Reactor Core         |
| Isolation Cooling (RCIC) system operation from the remote shutdown panel     |
| (RSDP) may not be available for safe shutdown of the unit.                   |
|                                                                              |
| A postulated fire that results in an electrical short of the Division 2      |
| 125/250 VDC distribution system to ground may cause a voltage control device |
| to fail integral to a RSDP instrument power supply inverter.  If the         |
| inverter fails as a result of the ground, no power supply would be available |
| for automatic or manual control of the RCIC turbine at the RSDP.  In         |
| addition, loss of the same inverter would also result in the loss of         |
| reactor, drywell and suppression pool monitoring instruments at the remote   |
| shutdown panel.                                                              |
|                                                                              |
| The current fire safe shutdown analysis credits only the RCIC system for     |
| post-fire inventory control during a worst case main control room fire.      |
| This analysis requires RCIC to be operational from the RSDP.   With this     |
| postulated loss of RCIC RSDP capability during a main control room fire,     |
| this event is reportable under 10CFR50.72(b)(3)(ii).                         |
|                                                                              |
| There were no actual safety consequences associated with this reportable     |
| event since there was no fire in the control room.  The design basis fire in |
| the control room assumes an all encompassing fire which is unlikely and      |
| would more likely be limited to a single panel.                              |
|                                                                              |
| An Alternate Safe Shutdown impairment has been established in accordance     |
| with station requirements.   Compensatory measures consist of calibrating a  |
| spare inverter for installation and expediting installation of a plant       |
| modification to remove the postulated failure mechanism.                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39464       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 12/19/2002|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 22:09[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        12/19/2002|
+------------------------------------------------+EVENT TIME:             [CST]|
| NRC NOTIFIED BY:  ERICK MATZKE                 |LAST UPDATE DATE:  12/19/2002|
|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LINDA HOWELL         R4      |
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 8-HOUR NOTIFICATION FOR UNANALYZED CONDITION                                 |
|                                                                              |
| "During a review of the Fort Calhoun Station fire protection program, it was |
| discovered that for a potential fire in two fire areas in the plant the      |
| protected train of reactor inventory control would not be free of fire       |
| damage.  During a postulated fire in either one of two fire areas the        |
| charging pump credited for maintaining hot shutdown reactor coolant          |
| inventory may be affected by a fire in one of the areas. This represents a   |
| technical noncompliance with 10CFR50 Appendix R section III.G.2 and does not |
| affect current plant operation.  As a compensatory measure, the plant is     |
| instituting hourly fire watches in the affected fire areas."                 |
|                                                                              |
| The licensee notified the Resident Inspector                                 |
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