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Event Notification Report for February 28, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           02/27/2003 - 02/28/2003



                              ** EVENT NUMBERS **



39613  39615  39623  39624  39625  



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|General Information or Other                     |Event Number:   39613       |

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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 02/24/2003|

|LICENSEE:  SPECTRO ANALYTICAL INSTRUMENTS       |NOTIFICATION TIME: 12:06[EST]|

|    CITY:  MARBLE FALLS             REGION:  4  |EVENT DATE:        02/13/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:             [CST]|

|LICENSE#:  L-02788-003           AGREEMENT:  Y  |LAST UPDATE DATE:  02/24/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |DAVID GRAVES         R4      |

|                                                |DOUG BROADDUS        NMSS    |

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

| NRC NOTIFIED BY:  JIM OGDEN                    |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:                                |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT - LEAKING SEALED SOURCE                               |

|                                                                              |

| The following information was obtained from the Texas Department of Health   |

| via facsimile:                                                               |

|                                                                              |

| "During routine service of an ASOMA (SPECTRO) Model 200, Serial No 4390, a   |

| wipe test was performed on a 20 millicurie Am-241 source, Serial No 13730W.  |

| Contamination of 0.035 microcuries was detected on the wipe.  The source is  |

| an AEA Technology (Amersham) Model AMC.D2 with a source product code         |

| AMCK2175.  It is encapsulated in an X10/2 capsule. The source was removed    |

| and is being returned to the manufacturer for evaluation.  All other         |

| interior components and exterior surfaces of the instrument were wipe tested |

| and found to have no contamination above the Licensee's minimum detection    |

| limit of 360 picocuries.  Agency was notified by telephone of the leaking    |

| source on February 13, 2003.  A written report was sent to this Agency that  |

| same date.  This incident was closed February 24, 2003.  No violations have  |

| been cited.                                                                  |

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|General Information or Other                     |Event Number:   39615       |

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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 02/24/2003|

|LICENSEE:  SPECTRO ANALYTIC INSTRUMENTS         |NOTIFICATION TIME: 16:46[EST]|

|    CITY:  MARBLE FALLS             REGION:  4  |EVENT DATE:        02/24/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        14:00[CST]|

|LICENSE#:  L-02788-003           AGREEMENT:  Y  |LAST UPDATE DATE:  02/24/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |DAVID GRAVES         R4      |

|                                                |ROBERT PIERSON       NMSS    |

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

| NRC NOTIFIED BY:  JIM OGDEN                    |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT - LEAKING SEALED SOURCE                               |

|                                                                              |

| The following information was obtained from the Texas Department of Health   |

| via facsimile:                                                               |

|                                                                              |

| "Leaking source was discovered during routine servicing of an ASOMA Model    |

| 200 analytical instrument, Serial No 4668. The instrument contained a sealed |

| Amersham 13 millicurie, Cm-244 source, Serial No 2695LM, Amersham Model No.  |

| CLCL. Last assay date was 08/15/95.  Leakage detected was from a routine     |

| wipe test which resulted in 0.0077 microcuries of removable contamination.   |

| The source is being prepared for return to the manufacturer for evaluation   |

| and disposal.  All other interior components and exterior surfaces of the    |

| instrument were wipe tested and found to have no contamination above the     |

| Licensee's minimum detection limit of 360 picocuries."                       |

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|Power Reactor                                    |Event Number:   39623       |

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| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/27/2003|

|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 17:15[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/27/2003|

+------------------------------------------------+EVENT TIME:        13:01[EST]|

| NRC NOTIFIED BY:  PETE SENA                    |LAST UPDATE DATE:  02/27/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |JOHN KINNEMAN        R1      |

|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          Y       58       Power Operation  |43       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| AUTOMATIC ACTUATION OF THE #2  EMERGENCY DIESEL GENERATOR                    |

|                                                                              |

| "This provides notification of an automatic actuation of the No. 2 Emergency |

| Diesel Generator (EDG) at Beaver Valley Power Station (BVPS) Unit No. 1      |

|                                                                              |

| "On 2/27/2003 at 1301 hours, BVPS Unit No. 1 was at 58 % power following a   |

| startup from a recent forced outage. The 'B' Main Feedwater Pump (MFP)       |

| tripped on overcurrent shortly after it was started. Concurrent with the MFP |

| trip, the breaker which feeds the non-safety related 'D' bus from the        |

| offsite power source also tripped, de-energizing the 'D' bus. [The 'D' bus   |

| supplies power to the 'B' MFP.] The loss of the 'D' bus caused the loss of   |

| power to the safety related Emergency 'DF' bus, which caused the No. 2 EDG   |

| to start and re-energize the Emergency 'DF' bus with all equipment properly  |

| loaded.                                                                      |

|                                                                              |

| "Control Room personnel entered Abnormal Operating Procedure 1.36.2, 'Loss   |

| of 4KV Emergency Bus.' Reactor Power was manually ramped back to 43 % power  |

| in response to this transient. Actions are being taken to re-energize the    |

| non-safety related 'D' bus from its offsite source. The EDG remains in       |

| operation with no abnormalities. The cause of the 'B' MFP trip is being      |

| investigated.                                                                |

|                                                                              |

| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(iv)(A) as   |

| an actuation of an emergency diesel generator which is part of the onsite    |

| emergency AC electrical power system. The NRC resident has been notified."   |

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|Power Reactor                                    |Event Number:   39624       |

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| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 02/27/2003|

|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 19:50[EST]|

|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        02/27/2003|

+------------------------------------------------+EVENT TIME:        17:31[CST]|

| NRC NOTIFIED BY:  RANDY HASTINGS               |LAST UPDATE DATE:  02/27/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS KOZAK         R3      |

|10 CFR SECTION:                                 |                             |

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

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|1     N          Y       100      Power Operation  |92       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS                          |

|                                                                              |

| "On 02/27/03 at 1731[CST] hours, Point Beach Unit 1 commenced an orderly     |

| reactor shutdown in response to TS [Technical Specifications] Action         |

| Statement 3.6.3.D.1, which requires the unit to be taken to Mode 3 in 6      |

| hours when two containment isolation valves are inoperable for greater than  |

| 1 hour. Valves 1SC-953 and 1SC-966B, pressurizer liquid space sampling       |

| containment isolation valves, were declared inoperable when leakage was      |

| evident past the shut valves. At 1748 hours, the pressurizer liquid space    |

| penetration flow path was verified as being isolated by shutting manual      |

| valve 1SC-952. The shutdown was terminated at 1751[CST] hours.               |

|                                                                              |

| "Earlier in the afternoon, it had been reported to the Control Room that the |

| reactor coolant primary sampling containment isolation valves (1SC-955 and   |

| 1SC-966C) were leaking through. The penetration flow path for these valves   |

| was isolated via shutting valve 1SC-954B. Further investigation revealed     |

| that leakage was still present. The leakage was isolated by shutting         |

| 1SC-952.                                                                     |

|                                                                              |

| "The 1D Pressurizer Heater Bank tripped during attempt to manually energize  |

| pressurizer heaters. Minimum required pressurizer heater capacity is         |

| maintained. Investigation is in progress."                                   |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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|Power Reactor                                    |Event Number:   39625       |

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| FACILITY: COLUMBIA GENERATING STATIREGION:  4  |NOTIFICATION DATE: 02/27/2003|

|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 23:37[EST]|

|   RXTYPE: [2] GE-5                             |EVENT DATE:        02/27/2003|

+------------------------------------------------+EVENT TIME:        19:45[PST]|

| NRC NOTIFIED BY:  CRAIG SLY                    |LAST UPDATE DATE:  02/27/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID GRAVES         R4      |

|10 CFR SECTION:                                 |                             |

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

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|2     N          Y       100      Power Operation  |80       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| UNIT COMMENCED TECH SPEC REQUIRED SHUTDOWN DUE TO INOPERABLE EDG             |

|                                                                              |

| "This ENS notification is made to report initiation of a plant shutdown      |

| required by the Columbia Generating Station Technical Specifications (TS's)  |

| pursuant to 10CFR 50.72(b)(2)(i).  This plant shutdown was initiated due to  |

| the inability to restore the Division I Emergency Diesel Generator (DG-1) to |

| operable status prior to exceeding the expiration of the Completion Time of  |

| TS LCO 3.8.1, Condition B.4.  Columbia Generating Station was granted        |

| enforcement discretion (NOED 03-4-001) from compliance with the completion   |

| time requirements of TS 3.8.1, Condition B.4, for an eleven-day period       |

| beginning on February 16, 2003 and ending February 27, 2003 at 9 p.m. (PST). |

| The enforcement discretion was granted to allow the replacement of a         |

| degraded DG-1 generator bearing.  Both generator bearings were replaced.     |

| However, during post maintenance tests to validate operability of DG-1,      |

| vibration levels for the new bearings showed evidence of an increasing       |

| trend.   Based on this, DG-1 is currently considered inoperable.  Even       |

| though the current vibration levels are very low, the plant has decided      |

| further testing and diagnosis is necessary to support a decision on DG-1     |

| operability.  Although the Completion Time of TS 3.8.1, Required Action B.4  |

| expires at 9 p.m., plant shutdown commenced at approximately 7:45 p.m.       |

| (PST), on February 27, 2003."                                                |

|                                                                              |

| The licensee informed the NRC resident inspector.                            |

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