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Event Notification Report for October 24, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/23/2002 - 10/24/2002

                              ** EVENT NUMBERS **

39311  39312  39315  39316  

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|Power Reactor                                    |Event Number:   39311       |
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| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 10/23/2002|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 12:15[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/23/2002|
+------------------------------------------------+EVENT TIME:        11:13[EDT]|
| NRC NOTIFIED BY:  TOM VEITCH                   |LAST UPDATE DATE:  10/23/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHRISTINE LIPA       R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| HIGH PRESSURE CORE SPRAY FAILED TO START ON DEMAND                           |
|                                                                              |
| The licensee was in the process of conducting normal testing when attempting |
| to start the High Pressure Core Spray Pump, it did not start.  The problem   |
| is being investigated at this time.  This notification is being made per 10  |
| CFR 50.72(b)(3)(v)(D) under accident mitigation.                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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|Hospital                                         |Event Number:   39312       |
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| REP ORG:  TENET HEALTH SYSTEMS GRADUATE        |NOTIFICATION DATE: 10/23/2002|
|LICENSEE:  TENET HEALTH SYSTEMS GRADUATE        |NOTIFICATION TIME: 16:38[EDT]|
|    CITY:  PHILADELPHIA             REGION:  1  |EVENT DATE:        10/22/2002|
|  COUNTY:                            STATE:  PA |EVENT TIME:        10:00[EDT]|
|LICENSE#:  37-28359-01           AGREEMENT:  N  |LAST UPDATE DATE:  10/23/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |FRANK COSTELLO       R1      |
|                                                |MELVYN LEACH         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KENT LAMBERT                 |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33               MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| MEDICAL MISADMINISTRATION-SOURCE RUPTURE DURING REMOVAL                      |
|                                                                              |
| A 830 microcurie Iodine 125 brachytherapy source ruptured while it was being |
| withdrawn from a patient's bladder during a prostate implant. The seed was   |
| removed and the patient's bladder was flushed. The flush solution measured   |
| 0.2 microcuries. Follow-up actions include evaluation of possible patient    |
| thyroid uptake and investigation to determine why the retrieval mechanism    |
| ruptured the source. The patient and prescribing physician have been         |
| informed of this event. The licensee also notified NRC Region 1 of the       |
| event.                                                                       |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39315       |
+------------------------------------------------------------------------------+
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 10/23/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:18[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/23/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:08[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/23/2002|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE BURGESS        R3      |
|  DOCKET:  0707002                              |MELVYN LEACH         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 91-01 RESPONSE BULLETIN 24 HOUR REPORT- LOSS OF ONE CONTROL (GEOMETRY)       |
|                                                                              |
| "On 10/23/02 @ 1108 hours, The Plant Shift Superintendent (PSS) was notified |
| of a violation of NCSA-0705_035 Control #23 in the X-705 Tunnel Basement     |
| Area. Control #23 states in part, 'At no time shall the depth of standing    |
| liquid, covering the entire floor area, exceed a depth of 1.7 inches.'       |
| Operations Personnel reported that as a result of a failure of the Facility  |
| Condensate System, the entire floor was covered by Non-Fissile Liquid        |
| greater than 1.7 inches in depth, thus constituting a loss of one Control    |
| (Geometry). All other Double Contingency Controls (Concentration,            |
| Interaction, and Other Passive Designs) were maintained throughout this      |
| event. The Failed System has been isolated and all Uranium Bearing Material  |
| Evolutions have been suspended pending repairs to the failed Facility        |
| Condensate System.                                                           |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
| This event has a low safety significance. The majority (99%) of the liquid   |
| on the floor area is overflowing steam condensate tank. The only credible    |
| way for additional Uranium bearing solution to be added to the liquid on the |
| floor is for a fissile solution storage bank to catastrophically fail. All   |
| uranium bearing solution evolutions in this work area have been suspended    |
| pending repairs.                                                             |
|                                                                              |
| "POTENTIAL CRITICALLY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW            |
| CRITICALITY COULD OCCUR):                                                    |
| One filled fissile solution storage bank fails while filled with fully       |
| enriched saturated U02F2 solution and all of the solution empties onto the   |
| floor of the tunnel basement floor mixing with the existing liquid to a      |
| minimum depth of 2 inches everywhere on the floor.                           |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
| The NCSA/NCSE controlled the floor of the tunnel basement area (Geometry),   |
| the condition of the floor of the tunnel basement (Geometry), and the depth  |
| of standing liquid allowed on the floor of the tunnel basement area.         |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
| Less than [. . .] grams of U-235 in the standing liquid on the floor of the  |
| tunnel basement area with a maximum enrichment of [. . .] wt% of U-235.      |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:                                             |
| The depth of standing liquid, as measured at the deepest location, exceeded  |
| the allowed depth of 1.7 inches.                                             |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
| No Safety System Activation resulted. All uranium bearing solution           |
| evolutions were suspended at 1108 hours as a result of this event and will   |
| remain as such pending repairs to the Facility Condensate System."           |
|                                                                              |
| The licensee has notified the NRC Resident Inspector and the onsite DOE      |
| Representative of the event.                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39316       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 10/24/2002|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 04:48[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        10/24/2002|
+------------------------------------------------+EVENT TIME:        01:22[EDT]|
| NRC NOTIFIED BY:  CALVIN WARD                  |LAST UPDATE DATE:  10/24/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       7        Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 MANUALLY TRIPPED DUE TO DECREASING STEAM GENERATOR WATER LEVEL        |
|                                                                              |
| "While performing a Plant Startup, following a refueling outage, a manual    |
| reactor trip was initiated due to decreasing Steam Generator Level. The trip |
| occurred at 0122 hours.  A main feedwater pump was being placed in service   |
| just prior to the trip.  The auxiliary Feedwater system was placed in        |
| service per plant procedures. The cause for decreasing S/G level is being    |
| investigated."                                                               |
|                                                                              |
| All rods fully inserted.                                                     |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
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