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Event Notification Report for February 26, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           02/25/2003 - 02/26/2003



                              ** EVENT NUMBERS **



39600  39601  39606  39607  39616  39617  39618  39619  39620  



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

|General Information or Other                     |Event Number:   39600       |

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

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

| REP ORG:  OHIO BUREAU OF RADIATION PROTECTION  |NOTIFICATION DATE: 02/20/2003|

|LICENSEE:  KEITHLY INSTRUMENTS, INC.            |NOTIFICATION TIME: 15:31[EST]|

|    CITY:  CLEVELAND                REGION:  3  |EVENT DATE:        02/19/2003|

|  COUNTY:                            STATE:  OH |EVENT TIME:             [EST]|

|LICENSE#:  GENERAL LIC.          AGREEMENT:  Y  |LAST UPDATE DATE:  02/20/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |JOHN MADERA          R3      |

|                                                |TOM ESSIG            NMSS    |

+------------------------------------------------+JOHN DAVIDSON        IAT     |

| NRC NOTIFIED BY:  MIKE SNEE                    |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| LOST AIR IONIZER                                                             |

|                                                                              |

| The following report was received by fax from the Ohio Department of         |

| Health:                                                                      |

|                                                                              |

| "The Bureau received a report of a lost generally licensed air ionizer       |

| [static eliminator].  The device was [an] NRD, LLC model P-2021-8101, serial |

| # A2BP733.  The device contained a Po-210 source with an activity of 1.25    |

| [millicuries] on 2/20/03."                                                   |

|                                                                              |

| The loss was attributed to inadequate training.                              |

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



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

|General Information or Other                     |Event Number:   39601       |

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

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

| REP ORG:  OHIO BUREAU OF RADIATION PROTECTION  |NOTIFICATION DATE: 02/20/2003|

|LICENSEE:  SCOTT PROCESS SYSTEMS, INC.          |NOTIFICATION TIME: 15:32[EST]|

|    CITY:  HARTVILLE                REGION:  3  |EVENT DATE:        01/08/2003|

|  COUNTY:                            STATE:  OH |EVENT TIME:        12:00[EST]|

|LICENSE#:  OH-0332077000         AGREEMENT:  Y  |LAST UPDATE DATE:  02/20/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |JOHN MADERA          R3      |

|                                                |TOM ESSIG            NMSS    |

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

| NRC NOTIFIED BY:  MIKE SNEE                    |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| ABNORMAL RADIOGRAPHY SOURCE RETRIEVAL                                        |

|                                                                              |

| The following information was received by fax from the Ohio Department of    |

| Health:                                                                      |

|                                                                              |

| "The licensee reported [an] abnormal radiography source retrieval due to a   |

| crimped guide tube.  A test piece fell on the guide tube during radiography  |

| operations in the licensee's radiography vault.  The licensee's source       |

| retrieval procedure was implemented and the source was successfully          |

| retrieved.  A total of 3 [millirem] was received by 2 individuals during     |

| this operation."                                                             |

|                                                                              |

| The source was Ir-192, 83 Curies, manufactured by AEA Technologies, model    |

| number 424-9, serial number 07686B.  The radiography camera is a Model 880   |

| manufactured by AEA Technologies, serial number D1163.                       |

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



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

|General Information or Other                     |Event Number:   39606       |

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

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

| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 02/20/2003|

|LICENSEE:  UNIVERSITY OF CALIFORNIA MEDICAL CENT|NOTIFICATION TIME: 19:12[EST]|

|    CITY:  ORANGE                   REGION:  4  |EVENT DATE:        02/20/2003|

|  COUNTY:                            STATE:  CA |EVENT TIME:        13:49[PST]|

|LICENSE#:  0278-30               AGREEMENT:  Y  |LAST UPDATE DATE:  02/20/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |KRISS KENNEDY        R4      |

|                                                |ROBERT PIERSON       NMSS    |

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

| NRC NOTIFIED BY:  GERRY FELDMAN                |                             |

|  HQ OPS OFFICER:  RICH LAURA                   |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| CALIFORNIA AGREEMENT STATE REPORT FOR MEDICAL EVENT AT UNIVERSITY OF         |

| CALIFORNIA                                                                   |

|                                                                              |

| "I took a call on a therapeutic misadministration from the RSO for UCIMC (LN |

| 0278-30). The incident involved the administration (via injection) of Y-90   |

| microspheres (25 microns) for the treatment of unresectable hepatic          |

| carcinoma. The intended dosage was 96.2 millicuries, and the administered    |

| dosage was approximately 38.48 millicuries (i.e., an underdose of 60%).      |

|                                                                              |

| "The delivery system consists of an injection system, connected to the vial  |

| containing the microspheres, which has one line leading to a receiving vial, |

| and another to the patient. The direction of the flow is determined by       |

| position of the valve connecting these two lines. Just beyond the vial       |

| containing the microspheres there are also two mounted detectors (like small |

| pocket chambers), which give a visual indication when the microspheres begin |

| moving out of the vial.                                                      |

|                                                                              |

| "The physicist was priming the system prior to a scheduled treatment. When   |

| the priming reaches the point that the microspheres begin to exit the vial,  |

| the valve is turned to direct the flow from the "receiving vial" to the      |

| patient. In this case, the physicist accidentally over-primed the system and |

| about 60% of the activity washed in the receiving vial. The physician, an    |

| authorized user, was also present during the treatment. They completed this  |

| treatment, and the physician is still reviewing whether it is necessary to   |

| perform another treatment to reach the prescribed dosage, or whether this    |

| treatment will be adequate as it stands.                                     |

|                                                                              |

| "The licensee is awaiting a report from the physician and physicist as to    |

| what might have caused this to occur. At the present time, they think it may |

| simply be that the physicist did not respond quickly enough to the           |

| indication on the detectors that activity was passing out of the isotope     |

| vial. That is, it may simply be a slow reflex problem. The manufacturer      |

| happened to be on site at the time of the incident, and indicated there had  |

| been two similar previous events (one allegedly at a hospital in PA), but no |

| further details on the events were obtained by the licensee."                |

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



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

|General Information or Other                     |Event Number:   39607       |

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

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

| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 02/20/2003|

|LICENSEE:  ALTA BATES MEDICAL CENTER            |NOTIFICATION TIME: 15:00[EST]|

|    CITY:  BERKELEY                 REGION:  4  |EVENT DATE:        02/20/2003|

|  COUNTY:                            STATE:  CA |EVENT TIME:             [PST]|

|LICENSE#:  0517-01               AGREEMENT:  Y  |LAST UPDATE DATE:  02/20/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |KRISS KENNEDY        R4      |

|                                                |ROBERT PIERSON       NMSS    |

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

| NRC NOTIFIED BY:  MELVA CLARIDGE               |                             |

|  HQ OPS OFFICER:  RICH LAURA                   |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| CALIFORNIA AGREEMENT STATE REPORT FOR MEDICAL EVENT AT ALTA BATES MEDICAL    |

| CENTER                                                                       |

|                                                                              |

| "Received a call today at about 1430 hours from [ ] who is one of Alta       |

| Bate's medical physicists (therapy department), to report a therapeutic      |

| misadministration involving I-125. The regular RSO is on leave. The patient  |

| was prescribed 0.35 millicuries I-125 for a brachytherapy procedure          |

| (prostate implant; involving 80+ seeds) on 2/19/03, but received 0.52        |

| millicuries, or an estimated 50% overdosage, because the calculation [was]   |

| done incorrectly."                                                           |

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



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

|Power Reactor                                    |Event Number:   39616       |

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

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

| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/24/2003|

|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 17:02[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/24/2003|

+------------------------------------------------+EVENT TIME:        15:48[EST]|

| NRC NOTIFIED BY:  PETE SENA                    |LAST UPDATE DATE:  02/25/2003|

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

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

|EMERGENCY CLASS:          UNUSUAL EVENT         |JOHN KINNEMAN        R1      |

|10 CFR SECTION:                                 |NADER MAMISH         IRO     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |TERRY REIS           NRR     |

|ACCS 50.72(b)(2)(iv)(A)  ECCS INJECTION         |ZENNOT               EPA     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|BOB SUMMER           R1      |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|DAVE KERN            R1      |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|1     A/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| UNUSUAL EVENT DUE TO MAIN STEAM LINE ISOLATION WITH SAFETY INJECTION         |

|                                                                              |

| The following information was received from the licensee via facsimile:      |

|                                                                              |

| "At 1548 [EST], on 2/24/03, Beaver Valley Unit 1 experienced an automatic    |

| reactor trip and safety injection on low steam line pressure.  An automatic  |

| main steam line isolation also occurred and all three main steam line        |

| isolation valves shut.  After the automatic actions occurred, operators      |

| noted that all three steam generator pressures appeared normal. Operators    |

| were dispatched to investigate in the field and found no indications of a    |

| steam leak.                                                                  |

|                                                                              |

| "Emergency procedure E-0, Response to Reactor Trip and Safety Injection, was |

| entered at 1548.  At 1600, the Shift Manager declared an unusual event.      |

| Initial notifications to state and local agencies were complete at 1609.     |

| Per procedure E-0, after meeting Safety Injection termination criteria, the  |

| Boron Injection Tank was isolated at 1603 and Safety Injection was           |

| terminated.                                                                  |

|                                                                              |

| "Initial review of computer information revealed that closure of the 'C'     |

| main steam isolation valve is the probable cause of the reactor trip, safety |

| injection and main steam isolation.                                          |

|                                                                              |

| "The gaseous release occurred due to tritium in the secondary and the fact   |

| that the turbine driven auxiliary feed pump is in service. No protective     |

| action recommendations were made.                                            |

|                                                                              |

| "All systems and equipment functioned as designed."                          |

|                                                                              |

| Technical Support Center is staffed but not activated.  All control rods     |

| inserted into the core.  The electrical grid is stable.  Unit 1 is stable.   |

| Core cooling is being accomplished via auxiliary feedwater and steam         |

| generator atmospheric dump valves.  There is previously identified steam     |

| generator "B" tube leakage of less than 0.1 gallons per day.                 |

|                                                                              |

| The NRC Resident Inspector has been notified.                                |

|                                                                              |

| * * * UPDATE AT 1735 EST ON 2/24/03 BY HOWIE CROUCH * * *                    |

|                                                                              |

| The licensee has terminated the Unusual Event.  They have re-established a   |

| pressurizer steam bubble.  The plant and electrical grid is stable.  Decay   |

| heat removal is via auxiliary feedwater and the steam generator atmospheric  |

| steam dumps.                                                                 |

|                                                                              |

| Notified FEMA, EPA, R1DO (Kinneman), DIRO (Mamish) and NRR EO (Reis).        |

|                                                                              |

| * * * UPDATE AT 0300 EST ON 2/25/03 TO MIKE RIPLEY  FROM P. SENA * * *       |

|                                                                              |

| The licensee updated the  event classification 10 CFR sections and current   |

| plant status.                                                                |

|                                                                              |

| "At 1735 [2/24/03], the Unusual Event was terminated.  This was based upon   |

| termination of the safety injection, completion of emergency operating       |

| procedure actions, and stabilization of plant conditions.  This was          |

| previously communicated to the NRC Operations Center at 1740.                |

|                                                                              |

| "As of 0245, on 2/25/03, Unit 1 remains in mode 3.  Heat removal is via the  |

| steam generator atmospheric steam release valves.  All main steam isolation  |

| valves remain shut as the event investigation continues.  The preliminary    |

| initiator of the event remains the inadvertent closure of 'C' Main Steam     |

| Isolation Valve.  The offsite release (due to tritium activity in the        |

| secondary) has been calculated and determined to be of minimal/no effect on  |

| the public.  The projected whole body dose was 5.12E-7 mrem [millirem].      |

| This is equivalent to 3.41 E-6 percent of the yearly Offsite Dose            |

| Calculation Manual Limit."                                                   |

|                                                                              |

| Notified FEMA, EPA, R1DO (Kinneman), DIRO (Mamish) and NRR EO (Reis)         |

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



!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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

|Power Reactor                                    |Event Number:   39617       |

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

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

| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 02/25/2003|

|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 06:56[EST]|

|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        02/25/2003|

+------------------------------------------------+EVENT TIME:        06:15[EST]|

| NRC NOTIFIED BY:  BRIAN McILNAY                |LAST UPDATE DATE:  02/25/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |CHARLES R. OGLE      R2      |

|10 CFR SECTION:                                 |                             |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|3     N          Y       60       Power Operation  |60       Power Operation  |

|4     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| DEGRADED PLANT ACCESS DUE TO CAR ACCIDENT ON SITE ACCESS ROAD                |

|                                                                              |

| "One car accident on access road to plant, however offsite.  Degraded        |

| emergency responder access."                                                 |

|                                                                              |

| The licensee will notify the NRC Resident Inspector.                         |

|                                                                              |

| * * * * RETRACTION RECEIVED AT 1059 EST ON 2/25/03 FROM MCILNAY TO RIPLEY *  |

| * *                                                                          |

|                                                                              |

| "Upon further review and in accordance with the guidance provided by         |

| NUREG-1022, Rev. 2, Section 3.2.13, Loss of Emergency Preparedness           |

| Capabilities, Turkey Point is retracting the NRC notification made under     |

| 10CFR 50.72(b)(3)(xiii) 0656 on February 25, 2003. As discussed in           |

| NUREG-1022, Loss of Offsite Response Capability considerations, NRC          |

| notification is required when a major loss of offsite response capability    |

| occurs. A major loss of offsite response capability is considered to include |

| loss of plant access for other than a short time for events that causes the  |

| access road to be impassible. The Turkey Point access road was limited to    |

| one lane (out of a normal two lane access) for 79 minutes, but at all times  |

| was accessible."                                                             |

|                                                                              |

| Notified R2 DO (C. Ogle).                                                    |

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



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

|Power Reactor                                    |Event Number:   39618       |

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

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

| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 02/25/2003|

|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 15:11[EST]|

|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        02/25/2003|

+------------------------------------------------+EVENT TIME:        14:10[EST]|

| NRC NOTIFIED BY:  ROBERT F. RAY                |LAST UPDATE DATE:  02/25/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       R2      |

|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  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| PHYSICAL SECURITY EVENT                                                      |

|                                                                              |

| Unescorted access granted inappropriately.  Immediate compensatory measures  |

| taken upon discovery.  Licensee notified NRC Resident Inspector.  Refer to   |

| HOO log for additional details.                                              |

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



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

|Power Reactor                                    |Event Number:   39619       |

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

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

| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 02/25/2003|

|    UNIT:  [2] [3] []                STATE:  NY |NOTIFICATION TIME: 15:28[EST]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        02/25/2003|

+------------------------------------------------+EVENT TIME:        07:50[EST]|

| NRC NOTIFIED BY:  CHARLIE HOCK                 |LAST UPDATE DATE:  02/25/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |JOHN KINNEMAN        R1      |

|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|MICHAEL JOHNSON      NRR     |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|2     N          Y       100      Power Operation  |100      Power Operation  |

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

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| LOSS OF ALL EMERGENCY SIRENS                                                 |

|                                                                              |

| The following information was obtained from the licensee via facsimile:      |

|                                                                              |

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

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

|                                                                              |

| "On February 25, 2003, at 0752 hrs [EST] an investigation revealed that the  |

| siren control system had apparently become inoperable at approximately 0650  |

| hrs. This condition affected the ability to sound all of the 154 sirens in   |

| the four counties of Orange, Putman, Rockland and Westchester for a period   |

| of 3 hours and 17 minutes. The siren system was successfully corrected,      |

| tested and returned to service at 1016 hrs.                                  |

|                                                                              |

| "The NRC Resident Inspector was notified of this event."                     |

|                                                                              |

| No state, local, or other government agencies were notified.                 |

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



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

|Power Reactor                                    |Event Number:   39620       |

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

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

| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 02/26/2003|

|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 02:05[EST]|

|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        02/26/2003|

+------------------------------------------------+EVENT TIME:        00:17[CST]|

| NRC NOTIFIED BY:  FRANSON                      |LAST UPDATE DATE:  02/26/2003|

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

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

|EMERGENCY CLASS:          UNUSUAL EVENT         |THOMAS KOZAK         R3      |

|10 CFR SECTION:                                 |MICHAEL JOHNSON      NRR     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |PATRICK HILAND       IRO     |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |AUSTIN               FEMA    |

|                                                |                             |

|                                                |                             |

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

|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                                   

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

| PLANT ENTERED A NOUE DUE TO BOTH EMERGENCY DIESEL GENERATORS BEING DECLARED  |

| INOPERABLE                                                                   |

|                                                                              |

| The licensee declared an unusual event at 0026 CST due to both Emergency     |

| Diesel Generators being inoperable resulting in the loss of on-site power    |

| capability.   At 0017 the "B" Diesel Generator failed to start during an     |

| attempt to verify operability as required by TS 3.7.b.2 since the "A" Diesel |

| Generator was out of service for maintenance.  They are investigating the    |

| cause for the no start of the "B" Diesel Generator.  The plant has 6 hrs to  |

| be in hot standby and the following 6 hrs to hot shutdown.                   |

|                                                                              |

| The NRC Resident Inspector will be notified.  State and local agencies were  |

| notified and there may be a press release.                                   |

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