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Event Notification Report for January 13, 2003




                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           01/10/2003 - 01/13/2003



                              ** EVENT NUMBERS **



39494  39498  39500  39501  39502  39503  39504  39505  



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|General Information or Other                     |Event Number:   39494       |

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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 01/07/2003|

|LICENSEE:  SPECTRO INSTRUMENTS                  |NOTIFICATION TIME: 18:32[EST]|

|    CITY:  MARBLE FALLS             REGION:  4  |EVENT DATE:        01/07/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        16:24[CST]|

|LICENSE#:  L02788                AGREEMENT:  Y  |LAST UPDATE DATE:  01/07/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |CHUCK CAIN           R4      |

|                                                |E. WILLIAM BRACH     NMSS    |

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

| NRC NOTIFIED BY:  HELEN WATKINS                |                             |

|  HQ OPS OFFICER:  ARLON COSTA                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT ON LEAKING SOURCES                                    |

|                                                                              |

| Texas Department of Health received a telephone notification from Spectro    |

| Instruments that two 50 microcurie Fe-55 sources were leaking.  Sources S/N  |

| 5069LG and S/N 6172LG were leak tested 0.4 microcuries and 0.13 microcuries  |

| respectively.                                                                |

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|Power Reactor                                    |Event Number:   39498       |

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| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 01/10/2003|

|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 12:47[EST]|

|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/10/2003|

+------------------------------------------------+EVENT TIME:        09:00[EST]|

| NRC NOTIFIED BY:  ALAN RABENOLD                |LAST UPDATE DATE:  01/10/2003|

|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |

|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  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| OFFSITE NOTIFICATION TO LOCAL COUNTY EMERGENCY AGENCIES                      |

|                                                                              |

| "At 0905, an injury occurred to a worker when the individual received 2nd    |

| degree burns to his forearms.  The worker was treated by the Company First   |

| Aid Team and released to Radiation Protection Personnel for deconning the    |

| individual.  The burn area had some contamination of 100 to 400 counts above |

| background.  The individual was deconned by our Radiation Protection         |

| Personnel and our Company Medical Personnel and is no longer contaminated.   |

| The individual was released back to work.                                    |

| The local County Emergency Management Agencies were notified of the          |

| potential for transportation of the individual to a local hospital, but      |

| transportation will not be required.  The individual has requested no        |

| medical treatment from the local hospital.  The local County Emergency       |

| Management Agencies were re-notified that the individual would not be        |

| transported."                                                                |

|                                                                              |

| The State of Ohio and local Counties were informed of this event.            |

|                                                                              |

| The NRC Resident Inspector was notified of this event by the licensee.       |

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|Power Reactor                                    |Event Number:   39500       |

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| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 01/10/2003|

|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 16:05[EST]|

|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        01/10/2003|

+------------------------------------------------+EVENT TIME:        11:56[CST]|

| NRC NOTIFIED BY:  AL BAILEY                    |LAST UPDATE DATE:  01/10/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |

|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   |

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

|                                                   |                          |

|2     M/R        Y       91       Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| MANUAL SCRAM DUE TO LOWERING REACTOR VESSEL WATER LEVEL                      |

|                                                                              |

| "This report is being made pursuant to 10CFR50.72(b)(2)(iv)(B), RPS          |

| Actuation (scram). At 11:56 CDST on January 10,2003, during normal           |

| operation, unit 2 was manually scrammed due to lowering vessel water level.  |

| The lowering water level was from the loss of the 2B Condensate pump and the |

| 2A & 2C Heater Drain pumps which resulted in a loss of both Turbine Driven   |

| Feed Pumps. ECCS equipment responded as expected (no automatic injection or  |

| starts). Hot Standby Mode of Operation was achieved with out difficulties    |

| and residual heat is being rejected to the condenser. No Safety Relief       |

| Valves actuated.                                                             |

|                                                                              |

| "Initial investigation revealed that the 2B condensate pump motor failed and |

| may have resulted in an electrical fluctuation on electrical buses resulting |

| in tripping some non-essential components. Further investigation, including  |

| troubleshooting is in progress for activities related to the condensate and  |

| heater drain pump loss."                                                     |

|                                                                              |

| All rods properly inserted into the core.  The licensee notified the NRC     |

| Resident Inspector.                                                          |

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|Power Reactor                                    |Event Number:   39501       |

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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 01/11/2003|

|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 07:15[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/10/2003|

+------------------------------------------------+EVENT TIME:        23:20[EST]|

| NRC NOTIFIED BY:  JOE SULLIVAN                 |LAST UPDATE DATE:  01/11/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD CONTE        R1      |

|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   |

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

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

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

|                                                   |                          |

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                                   EVENT TEXT                                   

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| LOSS OF ALL METEOROLOGICAL DATA FOR WIND SPEED, DIRECTION, AND TEMPERATURE   |

|                                                                              |

| This report is from the Salem/Hope Creek site.  Both Salem units and the     |

| Hope Creek unit are in power operation.                                      |

|                                                                              |

| "This 8-hour notification is being made to report that the Salem and Hope    |

| Creek site lost all meteorological data for wind speed, direction and        |

| temperature at 1520 [EST] on 1/10/03.  All three units are operating at 100% |

| power.  No actuations have taken place related to this event.  The cause of  |

| this loss is being investigated.  Procedural guidance is available to obtain |

| the necessary data from the national weather service should this data be     |

| necessary."                                                                  |

|                                                                              |

| The NRC resident inspector will be notified.                                 |

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|Power Reactor                                    |Event Number:   39502       |

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| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 01/11/2003|

|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 23:45[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/11/2003|

+------------------------------------------------+EVENT TIME:        21:45[EST]|

| NRC NOTIFIED BY:  LARRY TUMBLESON              |LAST UPDATE DATE:  01/12/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |

|10 CFR SECTION:                                 |JOHN DAVIDSON        IAT     |

|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                                   

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| OFFSITE NOTIFICATION TO FBI AND LOCAL LAW ENFORCEMENT                        |

|                                                                              |

| At 2345 EST on 1/11/03, the licensee reported that they had contacted the    |

| Charlotte, NC FBI and the Charlotte-Mecklenburg, NC police department        |

| concerning a report they received at 2145 EST on 1/11/03 from the Mt.        |

| Gilead, NC Volunteer Fire Department concerning a plastic traffic cone that  |

| was set on fire on Highway 73 approximately one-eighth mile east of the main |

| entrance road to the McGuire Station and approximately one-half mile from    |

| the owner-controlled area checkpoint on the entrance road.                   |

|                                                                              |

| The licensee will be informing the NRC resident inspector.                   |

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|Power Reactor                                    |Event Number:   39503       |

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| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 01/12/2003|

|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 18:14[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/12/2003|

+------------------------------------------------+EVENT TIME:        13:10[PST]|

| NRC NOTIFIED BY:  MR HARBOR                    |LAST UPDATE DATE:  01/12/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |CHUCK CAIN           R4      |

|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   |

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

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

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

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| LOSS OF MET TOWER DATA                                                       |

|                                                                              |

| "Event: On January 7, 2003 the Primary Meteorological (Met) Tower was        |

| removed from service to repair                                               |

| the 76-meter wind direction function. Removing the primary tower from        |

| service results in all                                                       |

| functions (i.e. wind speed, wind direction, and air temperature) being       |

| declared INOPERABLE.                                                         |

| On January 12, 2003 at 1310, the 60-meter air temperature for the Back-up    |

| Meteorological Tower                                                         |

| was declared INOPERABLE due to faulty readings.                              |

|                                                                              |

| "Effects on Plant: This has resulted in a loss of the capability to          |

| determine differential temperature for emergency                             |

| assessment (plume}.                                                          |

|                                                                              |

| "Cause: The cause of the faulty Back-up Met Tower 60-meter temperature       |

| indication is under                                                          |

| investigation. The Primary Met tower is INOPERABLE because it is disabled to |

| correct the 76-                                                              |

| meter wind direction function.                                               |

|                                                                              |

| "Actions Taken or Planned: 1) The portable meteorological monitoring system  |

| is being placed in-service per Diablo Canyon Power Plant (DCPP) Equipment    |

| Control Guideline (ECG) 40.l-B.1. This restores differential temperature     |

| monitoring capability. 2) DCPP maintenance personnel have been dispatched to |

| repair either the primary or back-up tower. The plant will remain in a 7 day |

| ECG until either towers air temperature monitoring function has been         |

| restored to OPERABLE status."                                                |

|                                                                              |

| The NRC Resident Inspector. has been notified.                               |

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|Power Reactor                                    |Event Number:   39504       |

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

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| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 01/12/2003|

|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 18:40[EST]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        01/12/2003|

+------------------------------------------------+EVENT TIME:        15:53[EST]|

| NRC NOTIFIED BY:  DAN HARDIN                   |LAST UPDATE DATE:  01/12/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

+------------------------------------------------+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     A/R        Y       94       Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| AUTOMATIC SCRAM ON LOWERING REACTOR VESSEL WATER LEVEL DUE TO FEED PUMP      |

| TRIP                                                                         |

|                                                                              |

| "Unit 1 was operating at 94 percent power (presently max power) when 1B      |

| Reactor Feed Pump (RFP) low oil pressure annunciator was received coincident |

| with 1B RFP trip at 1552. Reactor water level lowered and initiated an       |

| automatic SCRAM as the Reactor Operator was inserting a manual SCRAM at      |

| 1553. All systems initiated and isolated as required. A group 6 [containment |

| atmospheric and sampling] and Group 2 [drywell floor equipment drain         |

| isolation valves] isolation was received on low Reactor water level and      |

| verified. The Emergency Diesel Generators started as expected due to a       |

| reverse power lockout of the main generator. After the SCRAM the 1A RFP      |

| tripped on high water level. Prior to restarting a RFP a second SCRAM signal |

| was received on low level. The Reactor Core Isolation Cooling (RCIC) system  |

| was manually started to restore level while the reactor feed pump was being  |

| restarted. The preliminary investigation indicates that the running lube oil |

| pump on the 1B RFP tripped. The standby lube oil pump started however,       |

| apparently, did not recover lube oil pressure in time to prevent a trip of   |

| 1B RFP."                                                                     |

|                                                                              |

| All control rods properly inserted into the reactor core. The NRC Resident   |

| Inspector was notified.                                                      |

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



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|Power Reactor                                    |Event Number:   39505       |

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

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

| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 01/13/2003|

|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 02:48[EST]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/12/2003|

+------------------------------------------------+EVENT TIME:        23:04[EST]|

| NRC NOTIFIED BY:  RITA BRADDICK                |LAST UPDATE DATE:  01/13/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD CONTE        R1      |

|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       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| OPEN  DUCTWORK ACCESS PANEL PREVENTED MAINTAINING CONTROL ROOM POSITIVE      |

| PRESSURE                                                                     |

|                                                                              |

| "On January 12, 2003 at 2304, control room pressure was observed to be       |

| negative. At the time the "A" Control Room Emergency Filtration (CREF)       |

| system was tagged out for scheduled maintenance. The event was initiated     |

| when technicians opened an access panel on the "A" CREF control room air     |

| supply duct within the control room boundary to repair a gasket. This        |

| resulted in both "A" and "B" trains of CREF unable to perform its design     |

| safety function: specifically, maintaining the control room at a 1/8 inch    |

| water gauge positive pressure relative to adjacent areas. Without assurance  |

| of CREF system providing positive pressure in the control room, mitigating   |

| the consequences of an accident could have been prevented. Upon discovering  |

| the cause, technicians were ordered to close the access panel. Control room  |

| pressure promptly returned to a normal, positive value. Total time at        |

| negative pressure was ten minutes. No unexpected response was experienced.   |

| In addition to the "A" CREF train, the "A" Hydrogen/Oxygen analyzer was      |

| inoperable at the time of the event."                                        |

|                                                                              |

| The licensee has notified the NRC resident inspector.                        |

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