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Event Notification Report for January 22, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/18/2002 - 01/22/2002

                              ** EVENT NUMBERS **

38601  38631  38638  38639  38640  38642  


!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38601       |
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| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 01/01/2002|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 09:41[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/01/2002|
+------------------------------------------------+EVENT TIME:        00:42[CST]|
| NRC NOTIFIED BY:  STEVE WHEELER                |LAST UPDATE DATE:  01/21/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BLAIR SPITZBERG      R4      |
|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       10       Power Operation  |10       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| HIGH PRESSURE COOLANT INJECTION (HPCI) TURBINE DETERMINED TO BE
INOPERABLE   |
|                                                                              |
| The licensee determined during surveillance testing that the HPCI turbine    |
| was inoperable due to the minimum flow valve cycling open and closed due to  |
| problem with the associated flow switch.  The problem is being worked on.    |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| * * * RETRACTED AT 1736 EST ON 1/21/02 BY DAVID MADSEN TO FANGIE JONES * *   |
| *                                                                            |
|                                                                              |
| "Event Number 38601 reported a condition at Cooper Nuclear Station (CNS)     |
| where the High Pressure Coolant Injection (HPCI) was declared inoperable due |
| the minimum flow valve cycling open and closed. This condition occurred      |
| during surveillance testing of the HPCI turbine.                             |
|                                                                              |
| "This event was reported per 10CFR50.72(b)(3)(v)(D),  Accident Mitigation,   |
| on the basis that the cycling of the minimum flow valve (when HPCI injection |
| is required) could have resulted in injection flow below that required to    |
| maintain fuel integrity during certain transients or accidents. Subsequent   |
| investigation found the instrumentation initiating a signal to open the MOV  |
| would not reset. The requirement for the minimum flow to open for pump       |
| protection was always met. Existing analyses have determined that sufficient |
| margin exists to achieve adequate system flow even if the minimum flow valve |
| is in the full-open position. Also, the additional flow demands on the HPCI  |
| pump would not have resulted in a large enough increase in turbine speed     |
| that would have resulted in a turbine trip. For the scenario where the valve |
| may have cycled between open and closed position, the HPCI pump control      |
| system is capable of handling the change in flow without resulting in a      |
| turbine trip. Should HPCI have received a isolation signal or if the turbine |
| was manually tripped, the minimum flow valve would have closed.              |
|                                                                              |
| "Therefore, the above described condition did not result in a loss of safety |
| function for HPCI. Nebraska Public Power District has determined that this   |
| event is not reportable under the requirements of 10CFR50.72(b)(3)(v)(D),    |
| and as such, Event 38601 is retracted."                                      |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspection.  The R4DO (Dale  |
| Powers) has been notified.                                                   |
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|Other Nuclear Material                           |Event Number:   38631       |
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| REP ORG:  STORA ENSO NORTH AMERICA CORP.       |NOTIFICATION DATE:
01/16/2002|
|LICENSEE:  STORA ENSO NORTH AMERICA CORP.       |NOTIFICATION TIME:
09:56[EST]|
|    CITY:  WISCONSIN RAPIDS         REGION:  3  |EVENT DATE:        01/15/2002|
|  COUNTY:  WOOD                      STATE:  WI |EVENT TIME:        15:00[CST]|
|LICENSE#:  48-01117-01           AGREEMENT:  N  |LAST UPDATE DATE:  01/18/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTON VEGEL          R3      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLES CHAPMAN              |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A MISSING CESIUM-137 SOURCE AT A PAPER MILL (STORA ENSO
NORTH   |
| AMERICA CORP.) LOCATED IN WISCONSIN RAPIDS, WISCONSIN                        |
|                                                                              |
| During performance of a quarterly inventory on 01/15/02, the licensee        |
| discovered that a 200-millicurie cesium-137 source was missing.  It was used |
| as part of a fixed volume/density gauge which was mounted on a pipe.         |
| Apparently, the unit had been stored in the locked position on the pipe.     |
| The licensee reported that a paper machine dismantling project was ongoing   |
| near the previous location of the unit.  It is currently believed that the   |
| unit may either have been moved or dismantled and shipped somewhere.  The    |
| licensee's investigation is still in progress.                               |
|                                                                              |
| (Call the NRC operations officer for a licensee contact telephone number.)   |
|                                                                              |
|                                                                              |
| * * *  UPDATE ON 1/17/02 @ 1711 BY CHAPMAN TO GOULD  * * *                   |
|                                                                              |
| After further investigation the licensee has determined the source may have  |
| been stolen from the site. The licensee has notified the police and Region   |
| 3.  The device manufacturer will be notified.                                |
| Notified RDO 3 (Vegel), NMSS EO(Frant)                                       |
|                                                                              |
| * * * UPDATE ON 1/17/02 @ 1843 BY BREWSTER TO GOULD * * *                    |
|                                                                              |
| The licensee reported that they had been advised that an individual working  |
| for a contractor took the missing device.  They are further investigating    |
| the incident.                                                                |
|                                                                              |
| Notified RDO 3 (Vegel), NMSS EO(Frant)                                       |
|                                                                              |
| * * * UPDATE ON 1/18/02 @ 1513 BY CHAPMAN TO GOULD * * *                     |
|                                                                              |
| The licensee after further investigation and coordination with the local     |
| police have determined the the missing device was stolen.  Continuing        |
| investigation is ongoing.                                                    |
|                                                                              |
| Notified Reg 3 RDO (Vegel) and NMSS EO(Hickey)                               |
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|General Information or Other                     |Event Number:   38638       |
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| REP ORG:  LOUISIANA RADIATION PROTECTION DIV   |NOTIFICATION DATE:
01/18/2002|
|LICENSEE:  OWENSBY AND KRITIKOS                 |NOTIFICATION TIME: 12:39[EST]|
|    CITY:  SULPHUR                  REGION:  4  |EVENT DATE:        01/18/2002|
|  COUNTY:                            STATE:  LA |EVENT TIME:        11:00[CST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  01/18/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DALE POWERS          R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HENRY                        |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INDUSTRIAL RADIOGRAPHY ACCIDENT WITH POSSIBLE CONTAMINATION                  |
|                                                                              |
| Louisiana state licensee Owensby and Kritikos had an industrial radiography  |
| accident at the Citgo refinery in Lake Charles , La.   It appears that the   |
| source drive cable crossed an electric line and a spark exploded the         |
| Iridium-192 source.  They believe the source is in a safe condition, but     |
| there was considerable contamination outside the device.  They also believe  |
| some people may have contamination on their clothing which may have been     |
| tracked to other areas.  A health physicist has been dispatched to the       |
| scene.  The state also told the licensee to isolate the area.                |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38639       |
+------------------------------------------------------------------------------+
                         
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| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 01/19/2002|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 00:47[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        01/18/2002|
+------------------------------------------------+EVENT TIME:        21:23[CST]|
| NRC NOTIFIED BY:  M. HANNEMAN                  |LAST UPDATE DATE:  01/19/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTON VEGEL          R3      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| THREE OUT OF FOUR TIME DELAY SETTINGS FOR THE REACTOR HIGH PRESSURE      

  |
| ISOLATION CONDENSER INITIATION SWITCHES FOUND OUT OF CALIBRATION.           
|
|                                                                              |
|                                                                              |
| During performance of DIS 1300-01, Sustained High Reactor Pressure           |
| Calibration, three of the four time delay settings for the reactor high      |
| pressure Isolation Condenser initiation switches were found to be out of     |
| Technical Specification tolerance.  The maximum time delay allowed per       |
| Technical Specification Surveillance Requirement 3.3.5.2.3 is 15 seconds.    |
| The time delays for high pressure switches 2-263-53A, 53A, and 53C were      |
| 15.6, 15.4, and 15.4 seconds respectively.  The 2-263-53D switch was found   |
| in tolerance at 14.8 seconds.  Each time delay was adjusted to be back in    |
| tolerance.  This combination of three out-of-tolerance time delays could     |
| have prevented the Isolation Condenser from receiving an initiation signal   |
| within the 15 second Technical Specification required time limit.            |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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|Power Reactor                                    |Event Number:   38640       |
+------------------------------------------------------------------------------+
                         
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+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 01/19/2002|
|    UNIT:  [] [2] []                 STATE:  MI |NOTIFICATION TIME: 07:56[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/19/2002|
+------------------------------------------------+EVENT TIME:        00:05[EST]|
| NRC NOTIFIED BY:  S. KOSHAY                    |LAST UPDATE DATE:  01/19/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTON VEGEL          R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED AUTOMATIC  START OF TURBINE DRIVEN AUXILIARY FEEDWATER
PUMP       |
| (TDAFW) AFTER PLANT SHUTDOWN.                                                |
|                                                                              |
| After the scheduled reactor trip from 20% power in preparation for a         |
| refueling outage the steam generator water level lowered to approximately    |
| 17%.  This was lower than anticipated on the trip resulting in the Turbine   |
| Driven Auxiliary Feedwater Pump autostarting as a function of the steam      |
| generator's water level.  Both Motor Driven Auxiliary Feedwater (MDAFW)      |
| pumps had already been started.  Steam generator water levels rapidly        |
| recovered and the reactor coolant system cooled below 547 degrees F,  which  |
| is the normal no load temperature, to 540 degrees F.  The 7 degree cooldown  |
| below the Tave No Load Condition resulted in  Pressurizer Water Level shrink |
| and a letdown isolation.  The operators secured the TDAFW pump and throttled |
| the flows from the MDAFW pumps and restored reactor coolant system           |
| temperature and pressurizer inventory. The reactor coolant system cooldown   |
| and depressurization proceeded normally from that point on.                  |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+


+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38642       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
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| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 01/21/2002|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 19:50[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        01/21/2002|
+------------------------------------------------+EVENT TIME:        17:35[CST]|
| NRC NOTIFIED BY:  DUSTIN WRIGHT                |LAST UPDATE DATE:  01/21/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |ANTON VEGEL          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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM ON TURBINE GENERATOR LOAD REJECT                     |
|                                                                              |
| The licensee reported receiving a turbine generator load reject scram, cause |
| unknown at this time.  Generator lockout started the event.  A Group 2       |
| isolation occurred at +9" reactor water level.  All systems functioned as    |
| designed.  The scram and Group 2 have been reset and the plant will remain   |
| shutdown until further investigation is complete.                            |
|                                                                              |
| The licensee notified the NRC Resident Inspector, as well as the State and   |
| Local Governments.                                                           |
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