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Event Notification Report for January 14, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/11/2002 - 01/14/2002

                              ** EVENT NUMBERS **

38622  38623  38625  38626  38627  

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|Power Reactor                                    |Event Number:   38622       |
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 01/11/2002|
|    UNIT:  [] [2] []                 STATE:  NJ |NOTIFICATION TIME: 05:12[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/11/2002|
+------------------------------------------------+EVENT TIME:        04:00[EST]|
| NRC NOTIFIED BY:  JOHN GARECHT                 |LAST UPDATE DATE:  01/11/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RONALD BELLAMY       R1      |
|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  |65       Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| TECHNICAL SPECIFICATION SHUTDOWN DUE TO # 2A EMERGENCY DIESEL
GENERATOR NOT  |
| OPERATING PROPERLY.                                                          |
|                                                                              |
| "A unit shutdown was initiated at 0400 on 01/11/02 as required by Technical  |
| Specifications.  Technical Specification Action Statement 3.8.1.1.b action b |
| was entered at 0303 on 01/08/02 for scheduled maintenance on the 2A          |
| emergency diesel generator.  During post maintenance testing, oscillations   |
| associated with the generator voltage control system were observed.  The     |
| cause of the voltage oscillations has not been identified or corrected.      |
| Troubleshooting activities are on-going in an attempt to identify the        |
| cause.                                                                       |
|                                                                              |
| "The 2B and 2C emergency diesel generator surveillance tests were performed  |
| within 24 hours to evaluate for common cause failures.  A Common Cause       |
| Failure was not identified and the 2B and 2C surveillance tests were         |
| performed satisfactorily.                                                    |
|                                                                              |
| "Salem Unit Two will be in Mode 3 by 0930 on 01/11/02 and in Mode 5 by 1503  |
| on 01/12/02 as required by Technical Specifications.                         |
|                                                                              |
| "Salem Unit one is not affected by this event and remains in Mode 1 at       |
| 100%"                                                                        |
|                                                                              |
| The NRC Resident Inspector was notified of this event notification by the    |
| licensee.                                                                    |
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|Power Reactor                                    |Event Number:   38623       |
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| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 01/11/2002|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 11:23[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        01/11/2002|
+------------------------------------------------+EVENT TIME:        09:15[EST]|
| NRC NOTIFIED BY:  J. SCHORK                    |LAST UPDATE DATE:  01/11/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RONALD BELLAMY       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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFF-SITE SIRENS INOPERABLE IN YORK COUNTY                                    |
|                                                                              |
| "TMI is notifying the NRC Operations Center in accordance with 10 CFR        |
| 50.72(b)(3)(xiii) that a major loss of emergency preparedness capabilities   |
| for TMI has occurred. At 9:15 AM on Friday, January 11, 2001 during a test   |
| of all of the emergency sirens for the five (5) risk counties around TMI, it |
| was determined that the public emergency sirens for York County did not      |
| activate. Attempts to return the sirens to an operable status within 1 hour  |
| were unsuccessful. The sirens are currently inoperable.                      |
|                                                                              |
| "The apparent cause of the siren failure was a serial port failure on the    |
| computer that activates the York County signal transmitter. Therefore, no    |
| signal was transmitted to the 34 sirens for York County. Troubleshooting is  |
| in process to determine the exact cause of the failure.                      |
|                                                                              |
| "The siren test covered all of the five (5) risk counties around TMI. All of |
| the public emergency sirens for the other four risk counties for TMI         |
| (Cumberland, Dauphin, Lancaster and Lebanon) activated with the exception of |
| a single siren in Lancaster County. The inoperability of sirens for one-(1)  |
| of the five (5) risk counties around TMI impacts a large segment of the      |
| population. (continued on next page)                                         |
|                                                                              |
| "This event meets the criteria set forth in NUREG 1022 for a major loss of   |
| emergency offsite communications capability. The site Sr. Resident Inspector |
| has been informed of the event and the 8-hour report. The Pennsylvania       |
| Emergency Management Agency (PEMA) has been notified of the event. York      |
| County Emergency Management is aware of the event and has contacted the      |
| siren vendor. The siren failure event is being entered into the TMI-1        |
| corrective action program."                                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector as well as state and local  |
| authorities.                                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38625       |
+------------------------------------------------------------------------------+
                         
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| REP ORG:  U.S. AIR FORCE                       |NOTIFICATION DATE: 01/11/2002|
|LICENSEE:  U.S. AIR FORCE                       |NOTIFICATION TIME: 15:50[EST]|
|    CITY:  SANTA FE                 REGION:  4  |EVENT DATE:        01/10/2002|
|  COUNTY:                            STATE:  NM |EVENT TIME:             [MST]|
|LICENSE#:  NM-00624 AFB          AGREEMENT:  Y  |LAST UPDATE DATE:  01/11/2002|
|  DOCKET:  90000624                             |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BLAIR SPITZBERG      R4      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DAVID PUGH                   |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNKNOWN CONDITION OF SOURCES ON HELICOPTER THAT CRASHED                      |
|                                                                              |
| On 1/10/02 a H-60 US Air Force helicopter crashed north of Santa Fe, NM      |
| during a rescue effort.  The helicopter has 6 IBIS (In-flight Blade          |
| Inspection System) indicators, each containing 500 microcuries of Sr-90.     |
| The condition and actual location of the sources is unknown at this time.    |
| Teams will be out this weekend to access the crash site and try to locate    |
| the sources as part of the recovery efforts.                                 |
|                                                                              |
| The NRC Region 4 contact (Tony Gains) will be notified by the US Air Force.  |
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|Power Reactor                                    |Event Number:   38626       |
+------------------------------------------------------------------------------+
                         
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| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 01/11/2002|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 18:14[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        01/04/2002|
+------------------------------------------------+EVENT TIME:        09:32[CST]|
| NRC NOTIFIED BY:  MARK HANNEMAN                |LAST UPDATE DATE:  01/11/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INVALID ACTUATION OF PARTIAL GROUP II ISOLATION                              |
|                                                                              |
| "While performing Post Maintenance Testing (PMT) on Primary Containment      |
| Isolation Valve (PCIV) 2-9208A (Unit 2 Drywell Air Sample Valve) a fuse in   |
| the control circuit blew when the 2-9208A valve was given an open signal.    |
| This caused a partial Group II Isolation (Invalid Actuation) consisting of a |
| loss of indication to 14 PCIVs and the automatic closure of 11 PCIVs.        |
| Additionally the Traversing In-Core Probes (TIP) automatically retracted and |
| the 5 associated ball valves closed.                                         |
|                                                                              |
| "All plant systems responded as expected for the fuse opening. The fuse was  |
| replaced and the PCIVs that repositioned were returned to their normal       |
| position. The 2-9208A was removed from service. TIP runs were restarted.     |
| This event did not have any adverse effect on plant operation.               |
|                                                                              |
| "Troubleshooting found a shorted wire connection in the junction box for the |
| 2-9208A solenoid. The wire connection was repaired and the 2-9208A valve PMT |
| was performed satisfactorily."                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38627       |
+------------------------------------------------------------------------------+
                         
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+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 01/11/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 23:03[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/11/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        18:07[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/11/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |DAVID HILLS          R3      |
|  DOCKET:  0707001                              |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEVIN BEASLEY                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR REPORT - VALID ACTIVATION OF A TSR REQUIRED SAFETY SYSTEM            |
|                                                                              |
| "At 1807 CST, on 1-11-02 the Plant Shift Superintendent (PSS) was notified   |
| of an activation of the Water Inventory Control System (WICS) on #4          |
| autoclave In the C-360 building. Approximately seven minutes into the heat   |
| cycle the Hi Primary and HI Secondary Condensate alarms were received, and   |
| the autoclave went into containment as designed. The operators investigated  |
| the alarm with assistance from the Shift Engineer. Due to the alarm being    |
| received on the redundant Primary and Secondary probes at a point in the     |
| heat cycle when there is a high steam demand. Engineering determined this to |
| be a valid activation of the system. The autoclave was removed from service  |
| and the WICS was declared inoperable. Further investigation will be          |
| performed by the System Engineer and Instrument Maintenance to determine the |
| exact cause of the alarm. The purpose of the WICS is to limit the amount of  |
| water In the autoclave and is a safety system required by TSR 2.1.4.3.       |
|                                                                              |
| "The PSS determined that this event is a 24 Hour Event Report due to the     |
| valid activation of a TSR required safety system.                            |
|                                                                              |
| "The NRC Senior Resident Inspector has been notified of this event."         |
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