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Event Notification Report for July 23, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           07/22/2003 - 07/23/2003



                              ** EVENT NUMBERS **



40002  40007  40008  40009  40010  40011  



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|General Information or Other                     |Event Number:   40002       |

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| REP ORG:  NE DIV OF RADIOACTIVE MATERIALS      |NOTIFICATION DATE: 07/17/2003|

|LICENSEE:  HASTINGS STATE BANK                  |NOTIFICATION TIME: 10:42[EDT]|

|    CITY:  LINCOLN                  REGION:  4  |EVENT DATE:        07/17/2003|

|  COUNTY:                            STATE:  NE |EVENT TIME:             [CDT]|

|LICENSE#:  GL0377                AGREEMENT:  Y  |LAST UPDATE DATE:  07/17/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |LINDA SMITH          R4      |

|                                                |MATT HAHN            IAT     |

+------------------------------------------------+JOHN GREEVES         NMSS    |

| NRC NOTIFIED BY:  TRUDY HILL                   |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT - TWO LOST EXIT SIGNS THAT CONTAIN TRITIUM            |

|                                                                              |

| At 1042 EDT on 7/17/03,  a Nebraska Radiation Program Radiation Health       |

| Specialist reported that a licensee, Hastings State Bank, could not account  |

| for two tritium-based exit signs.   The bank is buying a building that       |

| previously housed a bank.  Nebraska State Radiation Program billed the new   |

| bank for the materials license associated with the exit signs.  The new      |

| branch manager of the Hastings Bank was unable to locate the exit signs in   |

| question.  In April of 1989, each sign contained 4.7 curies of tritium.  The |

| State of Nebraska will be visiting the site when the new bank opens in       |

| August.                                                                      |

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|Power Reactor                                    |Event Number:   40007       |

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| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 07/22/2003|

|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 11:13[EDT]|

|   RXTYPE: [3] CE                               |EVENT DATE:        07/21/2003|

+------------------------------------------------+EVENT TIME:        14:15[CDT]|

| NRC NOTIFIED BY:  MIKE BRANDON                 |LAST UPDATE DATE:  07/22/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |TROY PRUETT          R4      |

|10 CFR SECTION:                                 |                             |

|HFIT 26.73               FITNESS FOR DUTY       |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

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

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| FITNESS FOR DUTY                                                             |

|                                                                              |

| A Senior Reactor Operator licensed individual was determined to be under the |

| influence of illegal drugs during a random test.  The employee's access to   |

| the plant has been terminated.  Contact the HOO for additional details.      |

|                                                                              |

| The NRC Resident Inspector has been notified.                                |

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|Power Reactor                                    |Event Number:   40008       |

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| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 07/22/2003|

|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 16:10[EDT]|

|   RXTYPE: [1] GE-3                             |EVENT DATE:        07/22/2003|

+------------------------------------------------+EVENT TIME:        09:48[CDT]|

| NRC NOTIFIED BY:  GERRY STOCKHAM               |LAST UPDATE DATE:  07/22/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |ANNE MARIE STONE     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   |

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

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

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| HELB DOOR NOT LATCHED AS REQUIRED DUE TO PERSONNEL ERROR                     |

|                                                                              |

| "A High Energy Line Break (HELB) door was not latched as required.  This     |

| condition is being reported as an event that could have prevented the        |

| fulfillment of a safety function in accordance with 10CFR50.72(b)(3)(v)(A).  |

| The door is currently closed."                                               |

|                                                                              |

| The HELB door which separates two critical Motor Control Center [MCC] areas  |

| was unlatched for less than two (2) minutes.  The licensee will inform the   |

| state representative and has informed the NRC resident inspector.            |

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|Power Reactor                                    |Event Number:   40009       |

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| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 07/22/2003|

|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 17:24[EDT]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        07/22/2003|

+------------------------------------------------+EVENT TIME:        14:56[CDT]|

| NRC NOTIFIED BY:  DANA WHITE                   |LAST UPDATE DATE:  07/22/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |ANNE BOLAND          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  |

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

|                                                   |                          |

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                                   EVENT TEXT                                   

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

| OFFSITE NOTIFICATION TO OTHER GOVERNMENT AGENCIES CONCERNING MINOR OIL       |

| SPILL                                                                        |

|                                                                              |

| "On 7-22-03 at 1100, approximately 1 gallon of fuel oil was spilled during a |

| diesel generator fuel oil transfer surveillance test due to a leak at a hose |

| connection.  It is estimated that 1 quart of fuel oil went into a nearby     |

| floor drain.  As a result, a visible sheen of oil was observed on a swamp    |

| area on plant site.  This is a reportable spill to government agencies since |

| there is a visible sheen on "waters of the United States".  The US Coast     |

| Guard National Response Center was notified at 1456 on 7/22/03 and the       |

| Alabama Department of Environmental Management was notified at 1510 on       |

| 7/22/03."                                                                    |

|                                                                              |

| The licensee informed the NRC Resident Inspector.                            |

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|Power Reactor                                    |Event Number:   40010       |

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| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 07/22/2003|

|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 17:33[EDT]|

|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        07/22/2003|

+------------------------------------------------+EVENT TIME:        13:45[EDT]|

| NRC NOTIFIED BY:  TODD STRAYER                 |LAST UPDATE DATE:  07/22/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |DANIEL HOLODY        R1      |

|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       100      Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| AUTOMATIC REACTOR SCRAM DUE TO MAIN GENERATOR PROTECTIVE RELAY ACTUATION     |

|                                                                              |

| "With Unit 2 operating at 100% power, a Main Generator protective relay      |

| actuation occurred causing a Main Turbine trip and automatic Reactor         |

| Protection System (RPS) actuation.  The RPS signal received was Main Turbine |

| Control Valve Fast Closure.  RPS functioned as designed and all control rods |

| fully inserted.  Group II and III primary containment isolations went to     |

| completion and Standby Gas Treatment automatically started when reactor      |

| level reached the setpoint of 1" reactor level.                              |

|                                                                              |

| "At 1358, with Standby Gas Treatment System in operation, Main Steam Tunnel  |

| temperatures rose to the Group I isolation setpoint and a Group I isolation  |

| occurred.  There was not a steam leak that caused the Group I isolation.     |

| Following the Group I isolation, reactor level again lowered to the 1" RPS   |

| actuation and Group II/III isolation setpoint.  All control rods were fully  |

| inserted when this RPS actuation occurred.  With containment isolated, HPCI  |

| and RCIC were used to control reactor level.                                 |

|                                                                              |

| "At 1615 hours, while transitioning reactor level control to condensate, a   |

| RPS actuation, Group II, and Group III isolation occurred when reactor level |

| reached the setpoint of 1".  All control rods were fully inserted at the     |

| time.  All containment isolation valves that were opened following the       |

| initial actuation, isolated as expected.                                     |

|                                                                              |

| "All primary containment parameters are currently normal.  The crew has      |

| stabilized the plant and plant recovery actions have commenced.  The cause   |

| of the Main Generator protective relay actuation is not known at this        |

| time."                                                                       |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

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

|General Information or Other                     |Event Number:   40011       |

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

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

| REP ORG:  THERMO ELECTRON CORPORATION          |NOTIFICATION DATE: 07/22/2003|

|LICENSEE:  THERMO ELECTRON CORPORATION          |NOTIFICATION TIME: 18:13[EDT]|

|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        05/30/2003|

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

|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  07/22/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |DANIEL HOLODY        R1      |

|                                                |ANNE BOLAND          R2      |

+------------------------------------------------+KRISS KENNEDY        R4      |

| NRC NOTIFIED BY:  BARRY NICHOLSON              |JACK FOSTER          NRR     |

|  HQ OPS OFFICER:  NATHAN SANFILIPPO            |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| PART 21 NOTIFICATION DUE TO POSSIBLE DEFECT WITH THERMO WESTRONICS SERIES    |

| 2100C RECORDERS                                                              |

|                                                                              |

| The following report was received via fax:                                   |

|                                                                              |

| "July 21, 2003                                                               |

|                                                                              |

| "Subject: Thermo Westronics Model 2100C Series Recorders                     |

|                                                                              |

| "This letter is notification of a possible defect associated with Thermo     |

| Westronics Series 2100C recorders.  The Series 2100C is a DIN size           |

| programmable chart recorder utilized in control room applications of Nuclear |

| Power Plants.  The recorders in question were manufactured under the Thermo  |

| Westronics 10CFR50 Appendix B Quality Program between August 2002 and        |

| January 2003.                                                                |

|                                                                              |

| "On or about May 30, 2003, Thermo Electron determined that a random reset    |

| anomaly could possibly occur on the Series 2100C recorder.  This anomaly     |

| surfaced during the manufacture of three (3) commercial grade Series 2100    |

| recorders.  When the reset occurs, the recorder must be re-initialized to    |

| resume normal function.                                                      |

|                                                                              |

| "The root cause of the anomaly has been traced to a timing issue between the |

| CPU Printed Circuit Board Assembly (PCBA) and the Memory Module.  A 27C256   |

| EPROM, used as a decoder on the Memory Module, has changed manufacturers     |

| several times during the life of this product.  The EPROM as produced by the |

| original manufacturer is no longer available.                                |

|                                                                              |

| "Newer versions of this 27C256 EPROM typically function at faster speeds.    |

| The faster chip speed can cause a delay in the transition from "send" to     |

| "receive"' on the CPU Module and thereby result in the reset.  This reset    |

| event is random and does not occur on every recorder.                        |

|                                                                              |

| "After engineering evaluation, Thermo Electron has incorporated a            |

| modification to the CPU PCBA to ensure compatibility with the faster EPROM   |

| on the Memory Module.  This modification eliminates the timing delay and     |

| subsequent possibility of the reset.  Future shipments of this CPU Module    |

| shall incorporate this modification.                                         |

|                                                                              |

| "To ensure compatibility on previously installed recorders, the Memory       |

| Module shall only be offered as part of a kit that includes the newer        |

| version CPU PCBA.                                                            |

|                                                                              |

| "The scope of this notification includes ten (10) Series 2100C safety        |

| related recorders, all of which were thoroughly tested and did not exhibit   |

| this reset at the time of shipment.  However, since it is not possible to    |

| determine the exact manufacture date of the 27C256 EPROM used on these       |

| recorders, this notification is being issued.                                |

|                                                                              |

| .                                                                            |

| .  [Table removed]                                                           |

| .                                                                            |

|                                                                              |

| "Thermo Electron shall notify listed customers and make arrangements to      |

| implement the design modification, either by rework at the Thermo Electron - |

| Houston facility, or by providing replacement kits to the customer site.  It |

| is estimated that rework associated with the design modification should be   |

| completed within sixty (60) days, or as soon as Thermo Electron has been     |

| contacted by the identified customers."                                      |

|                                                                              |

| The affected sites include Laguna Verde, Mexico, Millstone, Catawba, and     |

| McGuire.                                                                     |

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