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Event Notification Report for November 25, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/22/2002 - 11/25/2002

                              ** EVENT NUMBERS **

38513  39387  39388  39389  39391  39392  39393  39394  39395  39396  39397  39399 
39400  39401  39402  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38513       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 11/23/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 12:30[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/23/2001|
+------------------------------------------------+EVENT TIME:        12:10[EST]|
| NRC NOTIFIED BY:  CHARLIE PIKE                 |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CAUDLE JULIAN        R2      |
|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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO FLORIDA STATE INVOLVING RECOVERED SEA TURTLE FROM    |
| UNIT 1 INTAKE STRUCTURE                                                      |
|                                                                              |
| "A sea turtle with no external injuries but appearing to be distressed was   |
| recovered from the Unit 1 Intake Structure.  The State Stranding Coordinator |
| for sea turtles has been contacted."                                         |
|                                                                              |
| * * * UPDATE 11/23/01 AT 1255EST FROM CHARLIE PIKE TO S. SANDIN * * *        |
|                                                                              |
| "Turtle has died."                                                           |
|                                                                              |
| The licensee informed both the State of Florida and the NRC Resident         |
| Inspector.                                                                   |
|                                                                              |
| * * * UPDATE 1413EST ON 12/3/01 FROM JACK BREEN TO FANGIE JONES * * *        |
|                                                                              |
| At approximately 1215 EST on 12/3/01, a report was made to the Florida       |
| Department of Fish and Wildlife concerning the recovery of an injured sea    |
| turtle from the plant's intake canal.  The turtle was a green sea turtle in  |
| the intake canal that appeared distressed and looked to have a wound from a  |
| boat motor on its back.  It will be transferred to the State for             |
| rehabilitation.                                                              |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  Notified           |
| R2DO(MacAlpine).                                                             |
|                                                                              |
| * * * UPDATE 1333EST ON 12/15/01 FROM JACK BREEN TO JOHN MACKINNON * * *     |
|                                                                              |
| At approximately 1215 EST on 12/15/01, a report was made to the Florida      |
| Department of Fish and Wildlife Conservation Commission to pick up a Green   |
| Turtle for rehabilitation. The Green Turtle was taken from the plant's       |
| intake canal, and the turtle appears to have shark bites.                    |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  Notified R2DO      |
| (Chuck Ogle).                                                                |
|                                                                              |
| * * * UPDATE 1450EST ON 01/06/02 FROM TULLIDGE TO JOHN MACKINNON * * *       |
|                                                                              |
| At 1350EST, a notification to the State of Florida Department of Fish and    |
| Wildlife Conservation Commission was made due to finding an injured          |
| Loggerhead sea turtle in Unit 1 intake. The sea turtle was transported       |
| offsite for rehabilitation. R2DO (Tom Decker) notified.                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| ***UPDATE 1330EST ON 4/23/02 FROM JACK BREEN TO RICH LAURA***                |
|                                                                              |
| The licensee rescued a  Loggerhead sea turtle from the intake canal.  The    |
| Florida Fish and Wildlife Conservation Commission was notified, and the      |
| turtle was turned over for rehabilitation.                                   |
|                                                                              |
| The NRC Resident Inspector was informed.  Notified R2DO (B. Bonser).         |
|                                                                              |
| ***UPDATE 1241EDT ON 5/29/02 FROM DAVE WILLIAMS TO RICHARD LAURA***          |
|                                                                              |
| The licensee reported that an offsite notification was made to the Florida   |
| Fish and Wildlife Conservation Commission concerning the discovery of a live |
| loggerhead sea turtle found in the plant's intake canal.  The turtle was     |
| lethargic and was sent for rehabilitation.                                   |
|                                                                              |
| The NRC Resident Inspector was informed.  Notified R2DO (K. Landis).         |
|                                                                              |
| ***** UPDATE AT 1125 EDT ON 06/01/02 FROM CHARLES MARPLE TO LEIGH TROCINE    |
| *****                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 1020 on 06/01/02, a notification was made to the Florida Fish and        |
| Wildlife Conservation Commission regarding a weak and emaciated Loggerhead   |
| turtle found in the plant intake barrier net.  The turtle will be sent       |
| off-site to the Marine Life Center for Rehabilitation."                      |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R2DO (Kerry Landis).                                    |
|                                                                              |
| *****UPDATE AT 11:53 EDT ON 6/2/02 FROM MARPLE TO LAURA******                |
|                                                                              |
| "A notification was made to the Florida Fish and Wildlife Conservation       |
| Commission regarding a dead small green sea turtle found in the tangle net.  |
| The turtle will be maintained on ice for a postmortem examination."          |
|                                                                              |
| The NRC resident inspector was notified. Notified R2DO (K. Landis)           |
|                                                                              |
| *****UPDATE AT 12:45 EDT ON 7/18/02 FROM BREEN TO LAURA******                |
|                                                                              |
| A notification was made to the State regarding a dead green sea turtle that  |
| was removed from the intake canal.                                           |
|                                                                              |
| The NRC resident inspector will be notified.                                 |
|                                                                              |
| Notified R2DO (C. Payne                                                      |
|                                                                              |
| ***UPDATE AT 1045 EDT ON 10/20/02 FROM KORTH TO NORRIS***                    |
|                                                                              |
| A Loggerhead turtle was retrieved from the plant's intake canal.  The turtle |
| was in need of rehabilitation.  Per the plant's turtle permit, the Florida   |
| Fish and Wildlife Conservation Commission (FWCC) was notified at 0927 EDT.   |
|                                                                              |
| The NRC Resident Inspector has been notified.                                |
|                                                                              |
| Notified R2DO (Barr)                                                         |
|                                                                              |
| * * * UPDATE AT 1338 EDT ON 10/22/02 FROM KELLY KORTH TO GERRY WAIG * * *    |
|                                                                              |
| A Loggerhead turtle was retrieved from the plant's intake canal.  The turtle |
| was in need of rehabilitation.  Per the plant's turtle permit, the Florida   |
| Fish and Wildlife Conservation Commission (FWCC) was notified at 1250 EDT.   |
|                                                                              |
| The NRC Resident Inspector will be notified by the licensee.                 |
|                                                                              |
| Notified R2DO (Bob Haag)                                                     |
|                                                                              |
| * * * UPDATE ON 11/22/2002 @ 1821 BY FIELDS TO GOULD * * *                   |
|                                                                              |
| The licensee notified the Florida Department of Environmental Protection of  |
| the recovery of a distressed loggerhead sea turtle from their intake canal.  |
| The turtle was taken to a rehabilitation facility.                           |
|                                                                              |
| The NRC Resident inspector will be notified.  Notified R2DO (David Ayres).   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39387       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 00:03[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/21/2002|
+------------------------------------------------+EVENT TIME:        19:55[CST]|
| NRC NOTIFIED BY:  TOM GORDON                   |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|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          Y       94       Power Operation  |94       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO LAW ENFORCEMENT                                      |
|                                                                              |
| Notifications were made to the FBI and Linn County Sheriff by the licensee.  |
| There was no impact on plant operations.                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| See the HOO Log for additional information.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39388       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 00:50[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        11/21/2002|
+------------------------------------------------+EVENT TIME:        19:53[EST]|
| NRC NOTIFIED BY:  KEVIN W. DAHM                |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OPRM CHANNELS DECLARED INOPERABLE                                            |
|                                                                              |
| "On November 21, 2002, Detroit Edison received confirmation from General     |
| Electric of a non-conservative analysis of OPRM Period Setpoint.             |
|                                                                              |
| "The non-conservative analysis affected the OPRM [Oscillating Power Range    |
| Monitor] Reactor Protection System (RPS) scram setpoint. The RPS setpoint    |
| may result in violating the Minimum Critical Power Ratio (MCPR) safety       |
| limits during a thermal-hydraulic instability.                               |
|                                                                              |
| "All OPRM channels have been declared inoperable. Technical Specifications   |
| 3.3.1.1 Action J requires an alternate method of detecting and suppressing   |
| thermal-hydraulic instabilities to be implemented within 12 hours.           |
| Alternate methods have been established, thus the Technical Specification    |
| has been satisfied.                                                          |
|                                                                              |
| "This report is being made in accordance with 10CFR50.72(b)(3)(v), any event |
| or condition that could have prevented the fulfillment of the safety         |
| function of a system needed to shut down the reactor and maintain it in a    |
| safe shutdown condition.                                                     |
|                                                                              |
| "This report is also being made in accordance with 10CFR50.72(b)(3)(vi).     |
| Events covered in paragraph (b)(3)(v) of this section may include one or     |
| more procedural errors, equipment failures, and/or discovery of design,      |
| analysis, fabrication, construction, and/or procedural inadequacies."        |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39389       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 06:27[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        11/21/2002|
+------------------------------------------------+EVENT TIME:        21:56[CST]|
| NRC NOTIFIED BY:  JOHN DAMPF                   |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|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     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALID SPECIFIED SYSTEM ACTUATION DURING MAINTENANCE                          |
|                                                                              |
| "At 2156, 11/21/02, while performing OSP-SB-0002E, a valid actuation signal  |
| was generated that caused the 'B' Reactor Trip Breaker to trip open. The     |
| cause of the event was the inadvertent mispositioning of a rotary selector   |
| switch utilized in the Solid State Protection System (SSPS) circuitry, which |
| enabled the P-10 permissive circuit.  Permissive P-10 is normally energized  |
| when power increases above 10 percent and this in turn enables a Reactor     |
| Trip permissive (P-7) for a low Pressurizer pressure reactor trip which has  |
| a setpoint of 1885 psig. Since the plant was in Mode 4 with primary system   |
| pressure at 970 psig, a valid Reactor Trip signal was generated and caused   |
| the Reactor Trip breaker to open. In addition to tripping the 'B' Reactor    |
| Trip breaker, one Source Range detector was de-energized due to energizing   |
| the P-10 permissive circuitry.  All systems actuated as expected.            |
| Performance of OSP-SB-0002B was terminated, the plant was stabilized, a      |
| recovery plan was developed, and the procedure was then successfully         |
| completed.  An Event Review Team (ERT) was assembled to determine the cause  |
| of the event.  Additional corrective action to be taken will be based upon   |
| recommendations provided by the ERT."                                        |
|                                                                              |
| The Resident Inspector will be notified by the licensee.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39391       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [1] [2] []                STATE:  MD |NOTIFICATION TIME: 13:34[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/22/2002|
+------------------------------------------------+EVENT TIME:        10:45[EST]|
| NRC NOTIFIED BY:  BRUCE SHICK                  |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     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          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO MARYLAND DEPARTMENT OF ENVIRONMENT              |
|                                                                              |
|                                                                              |
| Hydraulic oil spill from a Sky Lift resulted in 5 gallons of hydraulic fluid |
| deposited on the gravel and pavement below the Sky Lift.  The spill was from |
| a separated oil line.  No water ways or storm drains were involved.  ERPIP   |
| 3.0  Hazardous Material Spill and Spill Plan were implemented.  Maryland     |
| Department of Environment was notified of the hydraulic oil spill (quantity  |
| >26 gallons).   The event was terminated and the spill was cleaned up at     |
| 1300 hours.                                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39392       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  GENERAL ELECTRIC COMPANY             |NOTIFICATION DATE: 11/22/2002|
|LICENSEE:  GENERAL ELECTRIC COMPANY             |NOTIFICATION TIME: 13:43[EST]|
|    CITY:  SAN JOSE                 REGION:  4  |EVENT DATE:        11/22/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  11/22/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DALE POWERS          R4      |
|                                                |MOHAMED SHANBAKY     R1      |
+------------------------------------------------+DAVID AYRES          R2      |
| NRC NOTIFIED BY:  JASON POST (fax)             |BRENT CLAYTON        R3      |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |JACK FOSTER          NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| GENERAL ELECTRIC IDENTIFIED THE STABILITY OPTION III PERIOD BASED DETECTION  |
| ALGORITHM Tmin SPECIFICATION HAS A DEFECT                                    |
|                                                                              |
| "Stability solution Option III is implemented in the Oscillation Power Range |
| Monitor (OPRM).   Each OPRM channel contains 18 to 33 OPRM cells (depending  |
| upon plant size).   Each OPRM cell signal is summed from three to four       |
| closely spaced Local Power Range Monitor (LPRM) signals.   Each OPRM cell    |
| signal is processed through the Option Ill detection algorithms to determine |
| when a trip is required.   Trip of one OPRM cell causes its OPRM channel to  |
| trip, and when sufficient OPRM channels trip (one-out-of-two taken twice, or |
| two-out-of-four), a reactor scram is initiated to terminate the              |
| oscillation.                                                                 |
|                                                                              |
| "An OPRM trip is enabled for plant operation within the OPRM Armed Region as |
| defined on the power/flow map.  The Armed Region extends from natural        |
| circulation to 60% of rated core flow.  The licensing basis for the OPRM is  |
| to detect all expected oscillations within the OPRM Armed Region, and        |
| initiate a reactor trip to suppress the oscillation and provide Minimum      |
| Critical Power Limit (MCPR) safety limit protection.                         |
|                                                                              |
| "GE LTR NEDO-31960-A, Supplement 1, 'BWR Owners' Group Long - Term Stability |
| Solutions Licensing Methodology (Supplement 1),' November 1995, describes    |
| the Option III detection algorithms.  The Period Based Detection Algorithm   |
| (PBDA) provides licensing basis MCPR safety limit protection.  Other         |
| algorithms provide defense-in-depth protection.  The PBDA includes two       |
| parameters called Tmin and Tmax.  The PBDA will not evaluate oscillations if |
| the period is less than Tmin or greater than Tmax  because these would not   |
| be indicative of an expected coupled neutronic/thermal - hydraulic           |
| instability.   The LTR specifies that 'typical'  Tmin values are in the      |
| range of 1.0 to 1.4 seconds and 'typical' Tmax values are in the range of    |
| 3.0 to 3.5 seconds.                                                          |
|                                                                              |
| "The expected period of a coupled neutronic/thermal-hydraulic instability    |
| depends upon the fluid transit time through the core, and therefore depends  |
| upon core flow rate.  This has been demonstrated in reactor operation and is |
| predicted by GE computer models.   At high core flow, the expected           |
| oscillation period is shorter.   At low core flow rate, the expected         |
| oscillation period is longer.   The intent of the OPRM is that Tmin and Tmax |
| provide a wide range with adequate margin to the expected oscillation period |
| for operation within the OPRM Armed Region so that all expected coupled      |
| neutronic/thermal-hydraulic instabilities will be detected by the PBDA."     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39393       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [1] [2] []                STATE:  AR |NOTIFICATION TIME: 15:10[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        11/22/2002|
+------------------------------------------------+EVENT TIME:        08:56[CST]|
| NRC NOTIFIED BY:  HATHCOTE                     |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DALE POWERS          R4      |
|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       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| Unattended security weapon, compensatory measures put in place upon          |
| discovery.                                                                   |
|                                                                              |
| The NRC Resident Inspector was notified                                      |
|                                                                              |
| Contact HOO for additional details.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39394       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  UNITED STATES ARMY -ABERDEEN         |NOTIFICATION DATE: 11/22/2002|
|LICENSEE:  UNITED STATES ARMY                   |NOTIFICATION TIME: 15:31[EST]|
|    CITY:  ABERDEEN                 REGION:  1  |EVENT DATE:        10/31/2002|
|  COUNTY:                            STATE:  MD |EVENT TIME:             [EST]|
|LICENSE#:  91-30563-01           AGREEMENT:  Y  |LAST UPDATE DATE:  11/22/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |DAVID AYRES          R2      |
+------------------------------------------------+FRED BROWN           NMSS    |
| NRC NOTIFIED BY:  JOYCE KUYKENDALL             |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING CHEMICAL AGENT DETECTOR CONTAINING 30 MILLICURIES OF NICKEL-63       |
|                                                                              |
| During a conversation in a training exercise on October 31, 2002, the        |
| Radiation Safety Officer at Fort Bragg, NC  learned that a Unit had lost a   |
| GID-3 Chemical Agent Detector, containing 30 millicuries of Nickel-63,       |
| during a training exercise back in Oct/Nov of 2001.  The training area was   |
| searched and other Units were asked if they had possession of the missing    |
| Chemical Agent Detector. The detector was not found and is now it considered |
| missing.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39395       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FRAMATOME ANP                        |NOTIFICATION DATE: 11/22/2002|
|LICENSEE:  FRAMATOME ANP                        |NOTIFICATION TIME: 15:48[EST]|
|    CITY:  RICHLAND                 REGION:  4  |EVENT DATE:        11/22/2002|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  11/22/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DALE POWERS          R4      |
|                                                |BRENT CLAYTON        R3      |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JERALD HOLM                  |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE "POWERPLEX" MONITORING SOFTWARE CONTAINS AN ERROR                        |
|                                                                              |
| "The MCPR calculation using the SPCB correlation in the MICROBURN-B2 and     |
| MICROBURN-B codes and associated POWERPLEX monitoring software contains an   |
| error.  The error is in the determination of the axial adjustment factor for |
| use in the SPCB CPR [Critical Power Ratio] correlation.  This can lead to    |
| non-conservative CPR calculations when using the SPCB CPR correlation and    |
| potentially a violation of the MCPR [Minimum Critical Power Ratio] Technical |
| Specification operating limit since the POWERPLEX incore monitoring code may |
| under predict the MCPR for comparison to the operating limit.  This error in |
| MICROBURN-B2 and MICROBURN-B had no impact on the operating limit itself.    |
| The POWERPLEX incore monitoring software in use at River Bend, Grand Gulf,   |
| and LaSalle Unit 1 is impacted by this error."                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39396       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 16:18[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        11/22/2002|
+------------------------------------------------+EVENT TIME:        10:00[EST]|
| NRC NOTIFIED BY:  SCHORK                       |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INADVERTENT START OF "B" EMERGENCY DIESEL GENERATOR                          |
|                                                                              |
| "The cause of the inadvertent actuation was human error by an Auxiliary      |
| Operator.  The Auxiliary Operator mistakenly placed the "A" diesel generator |
| Engineering Safeguards Test Switch in the "Test" position, instead of        |
| placing the "B" EDG Engineering Safeguards Test Switch in the "Test"         |
| position.  During the "B" ESAS [Emergency Safeguards Actuation System]       |
| testing, a portion of the test sends a simulated start signal to the "B"     |
| EDG.  With the "B" EDG Engineering Safeguards test switch in the "Test"      |
| position, a light actuates when the simulated ESAS start signal is received, |
| indicating that the ESAS start signal had been received. However, the "B"    |
| EDG Engineering Safeguards Test Switch was not in the "Test" position.       |
| Therefore the "B" EDG started in accordance with the plant design.           |
|                                                                              |
| "A review of this event has determined that the event is reportable to the   |
| NRC in accordance with the guidance in NUREG 1022, Rev. 2. The signal to     |
| start the "B" EDG is not considered a "valid" signal because it was not a    |
| signal initiated by any actual plant condition or parameter.   Therefore,    |
| this event is considered to be an inadvertent actuation that was caused by   |
| an invalid signal and has been determined to be reportable to the NRC in     |
| accordance with 10 CFR 50.73 (a)(2)(iv)(A).                                  |
|                                                                              |
| "There was no effect on the TMl-1 plant due to the inadvertent start, beyond |
| the "B" Emergency Diesel Generator, The "B" EDG did not initiate block       |
| loading or any other sequence of events.  The "B" EDG was immediately        |
| shutdown and an event investigation was initiated. The "A" EDG remained      |
| operable throughout the event.   Throughout the event, the "A" EDG was       |
| capable of providing emergency alternating current including performing the  |
| required "fast start" and block loading in response to an ESAS auto-start    |
| signal, an undervoltage condition or loss of offsite power event.            |
|                                                                              |
| "As an immediate action, a test run of the "B" EDG is being performed for    |
| approximately 1 hour to confirm that the inadvertent "fast" start did not    |
| have any impact on its ability to provide emergency alternating current in   |
| the event of an ESAS auto-start signal, an undervoltage condition or loss of |
| offsite power.                                                               |
|                                                                              |
| "As stated above, an event investigation has been initiated.  The event will |
| be documented in the site corrective action program.   When the cause of the |
| human error is identified, appropriate corrective action will be taken and   |
| documented in the applicable corrective action report."                      |
|                                                                              |
| The Sr. Resident Inspector has been informed.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39397       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 16:29[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        11/22/2002|
+------------------------------------------------+EVENT TIME:        13:28[EST]|
| NRC NOTIFIED BY:  BAIN                         |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID AYRES          R2      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       94       Power Operation  |94       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NON-CONSERVATIVE ANALYSIS OF THE OSCILLATION POWER RANGE MONITOR PERIOD      |
| SETPOINT                                                                     |
|                                                                              |
| "On November 22, 2002, Brunswick Unit 1 received notification from General   |
| Electric of a Part 21 Non-Conservative Analysis of the Oscillation Power     |
| Range Monitor (OPRM) Period Setpoint.   The non-conservative analysis        |
| affects the OPRM Reactor Protection System setpoint which may result in      |
| inoperability of the OPRM Technical Specification function. Unit 2 does not  |
| have the OPRM system installed and is not affected by this condition.  Due   |
| to the implementation of Technical Specification required compensatory       |
| actions, there is minimal safety significance.                               |
|                                                                              |
| "All Unit 1 OPRM channels have been declared inoperable.  Technical          |
| Specification 3.3.1.1 Action I requires an alternate method of detecting and |
| suppressing thermal hydraulic instabilities to be implemented within 12      |
| hours. The alternate methods of detection and suppression are currently in   |
| place.   Activities are in progress to make the necessary adjustments to     |
| return the OPRM channels to an operable status."                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39399       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 21:17[EST]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        11/22/2002|
+------------------------------------------------+EVENT TIME:        16:50[CST]|
| NRC NOTIFIED BY:  JOHN J. REIMER               |LAST UPDATE DATE:  11/23/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|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       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE                                 |
|                                                                              |
| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or      |
| Condition that could have prevented fulfillment of a Safety Function needed  |
| to Mitigate the Consequences of an Accident.  During inspection of the High  |
| Pressure Core Spray (HPCS) 2VY02A area cooler, missing sheet metal screws    |
| were discovered.  This could have prevented the High Pressure Core Spray     |
| System (HPCS), a single train safety system, from performing its design      |
| function during a seismic event. This also made the Division 3 Diesel        |
| Generator inoperable.  This is reportable as an 8 hour ENS notification.     |
|                                                                              |
| "The required actions of Technical Specification (TS) 3.5.1 were entered on  |
| 11/22/02 at 1650 when the system was made inoperable.  TS 3.8.1 does not     |
| require Division 3 Diesel Generator operability if HPCS is declared          |
| inoperable.  Preparations to replace the missing sheet metal screws are in   |
| progress.  All other Emergency Core Cooling Systems are operable at this     |
| time.  An extent of condition review will be performed on all divisions for  |
| both units."                                                                 |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 11/23/02 @ 1333 BY CLARK TO GOULD * * *                      |
|                                                                              |
| "Subsequent to ENS notification EN #39399, repairs were affected to the HPCS |
| area cooler (2VY02A) and the system was returned to operable.   An extent of |
| condition inspection was performed on the remaining Unit 1 and Unit 2        |
| divisional area coolers.   During these inspections it was discovered that   |
| the Unit 1, Division 2 area cooler (1VY03A) was also missing several sheet   |
| metal screws.   The system was removed from service, repaired and returned   |
| to operable.   No problems were discovered on either of the two remaining    |
| Unit 1 divisional area coolers.                                              |
|                                                                              |
| During inspection on Unit 2, the Division 2 area cooler (2VY03A) was missing |
| all of its sheet metal screws.   At the time of discovery of the Division 2  |
| inoperability, the HPCS (Division 3) area cooler had already been repaired   |
| and declared operable.   It was determined however, that at some point both  |
| the HPCS (Division 3) and Division 2 Emergency Core Cooling System (ECCS)    |
| injection subsystems were under these conditions simultaneously.  Per        |
| Technical Specification (TS) 3.5.1 Bases when this combination of ECCS       |
| subsystems are inoperable, the plant is in a condition outside of the design |
| basis.                                                                       |
|                                                                              |
| Investigation of equipment and maintenance history will be performed to      |
| determine if any additional periods existed with multiple divisions under    |
| these conditions simultaneously.  At this time all divisional area coolers   |
| on both Units have been inspected.  Those with deficiencies have been        |
| repaired and declared operable."                                             |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 3 RDO(Clayton) was informed.                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39400       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 11/22/2002|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 22:54[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        11/22/2002|
+------------------------------------------------+EVENT TIME:        01:04[EST]|
| NRC NOTIFIED BY:  STEVE NICOLAOS               |LAST UPDATE DATE:  11/22/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NON-CONSERVATIVE ANALYSIS OF THE OSCILLATION POWER RANGE MONITOR PERIOD      |
| SETPOINT                                                                     |
|                                                                              |
| "On November 22, 2002, Nine-Mile Point Unit 2 received confirmation from     |
| General Electric of a Non-Conservative Analysis of the OPRM Period           |
| Setpoint.                                                                    |
|                                                                              |
| "The Non-Conservative Analysis affected the OPRM Reactor Protection System   |
| (RPS) scram setpoint.  The RPS setpoint could have resulted in violating the |
| Minimum Critical Power Ratio (MCPR) safety limits during a thermal -         |
| hydraulic instability.                                                       |
|                                                                              |
| "At the time of the notification Nine-Mile Point Unit 2 was in Mode 4 cold   |
| shutdown.  Upon notification, the OPRM's were immediately declared           |
| inoperable.                                                                  |
|                                                                              |
| "On November 22, 2002, the OPRM's were adjusted to satisfy the vendor        |
| recommendations and the OPRM's have since been declared operable.            |
|                                                                              |
| "This report is being made in accordance with Nine-Mile Point Unit 2's       |
| Operating License 2.C.2 Technical Specification and Environmental Protection |
| Plan.  Nine-Mile Point Nuclear Station, LLC shall operate the facility in    |
| accordance with Technical Specifications."                                   |
|                                                                              |
| The NRC Resident Inspector has been notified of this event                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39401       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 11/23/2002|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 07:37[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        11/23/2002|
+------------------------------------------------+EVENT TIME:        03:32[EST]|
| NRC NOTIFIED BY:  ALISON MACKELLAR             |LAST UPDATE DATE:  11/23/2002|
|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID AYRES          R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       85       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO LOW-LOW STEAM GENERATOR LEVEL                  |
|                                                                              |
| "At 0332 hours, with Surry Power Station Unit 2 at 85% reactor power, a low  |
| low S/G level signal was received which resulted in an automatic reactor     |
| trip.  Immediately prior to the trip, the Turbine Stop and Governor Valves   |
| were being manipulated for a scheduled Governor Valve Freedom Test.  While   |
| closing Turbine Governor Valve #3 the Turbine Valve Limiter failed to zero   |
| closing all four governor valves. This led to the automatic reactor trip.    |
|                                                                              |
| "IRPI indications for six control rods indicated between 11 and 20 steps     |
| following the trip.  [Unit 2 was] borated as necessary to ensure adequate    |
| shutdown margin.  All other control rods fully inserted into the core as     |
| designed. The shutdown margin for Unit 2 was determined to be satisfactory.  |
| Auxiliary feedwater automatically initiated [ESFAS] as designed on low low   |
| steam generator level.  All three Main Steam Trip Valves were manually       |
| closed due to inability to verify full closed indication on #1 Turbine Stop  |
| Valve.  Primary RCS temperature decreased to approximately 547 degrees       |
| following the reactor trip and is currently stable on the Secondary Power    |
| Operated Relief Valves.                                                      |
|                                                                              |
| "No primary safety or power operated relief valves were actuated during the  |
| event.  No indication of primary to secondary leakage exists, therefore no   |
| adverse radiological consequences resulted from this event.                  |
|                                                                              |
| "All electrical busses transferred properly following the trip and all       |
| emergency diesel generators are operable. There were no radiation releases   |
| due to this event, nor were there any personnel injuries or contamination    |
| events. The cause of the event is being investigated.                        |
|                                                                              |
| "Unit 2 is currently at Hot Shutdown with RCS temperature being maintained   |
| at approximately 547 degrees.                                                |
|                                                                              |
| "Unit 1 was not affected by this event and remains stable at 100% power      |
| operations.                                                                  |
|                                                                              |
| "This event is being reported in accordance with 10CFR50.72(b)(2)(iv)(b)."   |
|                                                                              |
| The Resident Inspector was notified of this event.                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39402       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 11/24/2002|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 10:29[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/24/2002|
+------------------------------------------------+EVENT TIME:        08:14[CST]|
| NRC NOTIFIED BY:  DUSTIN PRICE                 |LAST UPDATE DATE:  11/24/2002|
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|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          Y       94       Power Operation  |94       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOTIFICATION OF OFFSITE AUTHORITIES OF FIRE IN ONSITE WAREHOUSE              |
|                                                                              |
| "At approximately 08:14, Sunday, November 24,2002, East Warehouse Sprinkler  |
| System Initiated annunciator alarmed. Seconds later, 1P-48 Electric Fire     |
| Pump initiated as indicated on panel 1C40.  The Second Assistant was         |
| dispatched and reported the sprinkler system in operation and a portion of   |
| the East Warehouse filled with smoke. The on-site fire brigade was assembled |
| at this time.                                                                |
|                                                                              |
| "The Fire Brigade Leader, after reaching the East Warehouse, reported no     |
| open flames and smoke emanating from a popcorn machine located in a          |
| breakroom in the warehouse.  As a precaution, off-site assistance was        |
| requested of the Palo Fire Department.  Currently the fire is out and the    |
| building is being ventilated. This notification is being made due to         |
| notification of offsite fire department and local law enforcement            |
| agencies."                                                                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+