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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  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39494       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39498       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39500       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39501       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39502       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39503       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39504       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.                        |
+------------------------------------------------------------------------------+