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Event Notification Report for December 23, 2002



                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/20/2002 - 12/23/2002

                              ** EVENT NUMBERS **

39457  39465  39466  39467  

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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                                   
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| 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:   39465       |
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| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 12/20/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 20:04[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        12/20/2002|
+------------------------------------------------+EVENT TIME:        19:15[EST]|
| NRC NOTIFIED BY:  SHARON DAVIS                 |LAST UPDATE DATE:  12/20/2002|
|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+
+------------------------------------------------+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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| UNANALYZED CONDITION                                                         |
|                                                                              |
| "Inspection of the Harris Nuclear Plant (HNP) Safe Shutdown Analysis (SSA)   |
| in Case of Fire identified that for postulated fires in three fire areas,    |
| the design and compensatory actions assumed by the Safe Shutdown Analysis    |
| would not ensure a protected train of equipment would remain available. This |
| condition constitutes noncompliance with the HNP FSAR and is reportable as   |
| an unanalyzed condition as described in 10CFR50.72.                          |
|                                                                              |
| "The inspection identified that postulated fires could cause spurious        |
| actuation of components potentially resulting in loss of the Charging/Safety |
| Injection Pump (CSIP) assumed to be protected by the Safe Shutdown Analysis. |
| The fires were postulated to cause spurious closure of valves in the suction |
| and/or discharge flowpaths for the protected CSIP prior to implementation of |
| the preplanned actions designed to preserve these flowpaths. The protected   |
| CSIP could be lost if it was in service at the time of the postulated fire.  |
|                                                                              |
| "The plant is instituting several interim compensatory measures to minimize  |
| the impact of the postulated fires. These measures include aligning the      |
| Charging System and de-energizing certain valves to minimize susceptibility  |
| to mal-operation of components, and posting a fire watch in fire areas of    |
| concern."                                                                    |
|                                                                              |
| The three areas of concern for the postulated fires are in the 261 RAB       |
| elevation north-south hallway.  The cable spreaders in this area constitute  |
| the susceptible equipment.                                                   |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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|Power Reactor                                    |Event Number:   39466       |
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| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 12/22/2002|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 00:18[EST]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        12/21/2002|
+------------------------------------------------+EVENT TIME:        20:35[EST]|
| NRC NOTIFIED BY:  DAN FORRY                    |LAST UPDATE DATE:  12/22/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |J. BRADLEY FEWELL    R1      |
|10 CFR SECTION:                                 |DAVID MATTHEWS       NRR     |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|ACCS 50.72(b)(2)(iv)(A)  ECCS INJECTION         |                             |
|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       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR  SCRAM AFTER EHC FAILURE                                   |
|                                                                              |
| At 2035, an EHC failure occurred that caused multiple bypass valves to open. |
| Reactor pressure dropped resulting in a Group 1 isolation (closure of        |
| MSIV's) which caused a reactor scram.  Lowest pressure was approximately     |
| 850#.  Level dropped through Lo Level (1"), resulting in Group 2/3 PCIS      |
| isolation.  Level continued to Lo Lo Level (-48"), resulting in ECCS         |
| actuation and injection (HPCI & RCIC).  ARI also initiated resulting in trip |
| of both Recirculation pumps.  Plant is stabilized and preceding to cold      |
| shutdown.                                                                    |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector.                        |
|                                                                              |
| The plant currently has MSIV's shut due to 3 Bypass valves open and are      |
| maintaining pressure control with HPCI & RCIC.                               |
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|Power Reactor                                    |Event Number:   39467       |
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| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 12/23/2002|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 02:53[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        12/23/2002|
+------------------------------------------------+EVENT TIME:        01:59[EST]|
| NRC NOTIFIED BY:  BARRY DOE                    |LAST UPDATE DATE:  12/23/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |J. BRADLEY FEWELL    R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     A/R        Y       100      Power Operation  |0        Hot Standby      |
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                                   EVENT TEXT                                   
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| AUTOMATIC REACTOR TRIP CAUSED BY MAIN GENERATOR TRIP                         |
|                                                                              |
| Automatic reactor trip caused by main generator backup relay protection      |
| trip.  The plant currently is stable in mode 3 with Auxiliary Feedwater in   |
| service for decay heat removal.  All control rods fully inserted, no primary |
| relief valves lifted and no ECCS actuation occurred.  The Licensee reports   |
| that the electrical grid is stable and all emergency diesels are available.  |
|                                                                              |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector.                        |
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