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Event Notification Report for October 10, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/09/2002 - 10/10/2002

                              ** EVENT NUMBERS **

39260  39262  39263  39264  39265  

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|Power Reactor                                    |Event Number:   39260       |
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| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 10/09/2002|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 03:31[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        10/09/2002|
+------------------------------------------------+EVENT TIME:        03:07[EDT]|
| NRC NOTIFIED BY:  LOU GAREAU                   |LAST UPDATE DATE:  10/09/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |NADER MAMISH         IRO     |
|                                                |JIM DUNKER           FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| UNUSUAL EVENT DECLARED DUE TO FIRE IN PROTECTED AREA LASTING GREATER THAN 10 |
| MINUTES                                                                      |
|                                                                              |
| "Unusual event was classified based on a fire in the protected area lasting  |
| > 10 minutes.  The fire started in the motor of the 'B' circulating water    |
| pump.  It was 'contained' to that location (the CW pump motor).  Motor       |
| [is]still smoldering, [but] it is controlled and contained.  Steam Generator |
| Blowdown system isolated due to high flash tank level.  Multiple rad         |
| monitors went into alarm due to voltage surge."                              |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| The Licensee reported that no offsite assistance was requested and that the  |
| State (NH) was notified.                                                     |
|                                                                              |
| ***UPDATE JIM HILL TO JOHN MacKINNON 0614 EDT 10/9/02***                     |
|                                                                              |
| The Unusual Event was Terminated at 0547 EDT.                                |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector and the State(NH).      |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39262       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COLUMBIA GENERATING STATIREGION:  4  |NOTIFICATION DATE: 10/09/2002|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 15:30[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        08/16/2002|
+------------------------------------------------+EVENT TIME:        02:54[PDT]|
| NRC NOTIFIED BY:  CRAIG SLY                    |LAST UPDATE DATE:  10/09/2002|
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JONES        R4      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INVALID SYSTEM ACTUATION DUE TO LOSS OF RPS BUS "A"                          |
|                                                                              |
| "On August 16, 2002 at approximately 0254 hours, a loss of Reactor           |
| Protection System (RPS) Bus A occurred while operators were attempting to    |
| reset a half-scram on the A2 logic channel of the RPS. The A2 logic reset    |
| attempt was required in accordance with a surveillance test procedure that   |
| was in progress, PPM OSP-RPS-Q402, MSIV Closure Scram Functional. Upon loss  |
| of RPS Bus A, control room operators entered Abnormal Procedure ABN-RPS,     |
| Loss of RPS, and an operator was dispatched to investigate the problem.      |
|                                                                              |
| "The operator investigating the problem discovered that the Motor Generator  |
| Set (RPS-MG-A) that supplies RPS Bus A was running with both of its          |
| electrical protection assemblies (EPAs) in the tripped position. In          |
| accordance with procedure ABN-RPS, operators transferred RPS Bus A to its    |
| alternate power supply and then reset the half-scram and associated          |
| containment outboard isolations. The operators then exited PPM OSP-RPS-Q402. |
| The follow-up investigation found that the loss of the RPS Bus A was due to  |
| a trip of the RPS-MG-A output breaker (RPS-MG-CB1) on over-voltage. The      |
| output breaker trip caused both downstream Electrical Protection Assemblies  |
| (RPS-EPA-3A and RPS-EPA-3C) to trip. This is the expected and required       |
| response for RPS-EPA-3A and RPS-EPA-3C."                                     |
|                                                                              |
| The loss of power to RPS Bus A had the following effects on the plant:  An   |
| actuation of RPS trip system A (Half-Scram), Main Steam Line Radiation       |
| Monitors A and C lost power; a trip of the Balance of Plant isolation logic  |
| in control room relay Cabinet RC-1; an outboard primary containment          |
| isolation signal was received by the following  (valves closed or were       |
| already closed): Main Steam Line  Drain Valves, Reactor Water Sample Valve,  |
| Drywell Floor and Equipment Drain Isolation Valves, Residual Heat Removal    |
| (RHR) Discharge to Radwaste and  Heat Exchanger Sample Isolation Valves, RHR |
| Shutdown Cooling (SDC) Reactor Head Spray Isolation Valve, SDC Return        |
| Valves, Reactor Water Cleanup (RWCU) Suction Valve.  All of these plant      |
| equipment responses were as expected and per plant design.                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   39263       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ST PATRICK HOSPITAL                  |NOTIFICATION DATE: 10/09/2002|
|LICENSEE:  ST PATRICK HOSPITAL                  |NOTIFICATION TIME: 16:38[EDT]|
|    CITY:  MISSOULA                 REGION:  4  |EVENT DATE:        08/30/2002|
|  COUNTY:                            STATE:  MT |EVENT TIME:             [MDT]|
|LICENSE#:  121677302             AGREEMENT:  N  |LAST UPDATE DATE:  10/09/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JONES        R4      |
|                                                |ERIC LEEDS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BREWER                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33               MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION                                                    |
|                                                                              |
| A patient was receiving a gynecological implant of Cs-137 which had  the     |
| incorrect activity entered into the computer.   The calibrated activity was  |
| inadvertently entered instead of the current activity.   The patient was     |
| also receiving external beam therapy from a linear accelerator along with    |
| the Cs-137 implant.  With the incorrect data being entered into the          |
| computer, the patient received a total dose(external and implant) which      |
| deviated below the prescribed dose by approximately 16%.   The implant       |
| dosage, however had greater than a 20% deviation less than the prescribed    |
| dose.   This medical misadministration was discovered on 10/09/02 @ 1620 MT. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39264       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 10/09/2002|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 17:12[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        10/09/2002|
+------------------------------------------------+EVENT TIME:        13:59[EDT]|
| NRC NOTIFIED BY:  LEONE                        |LAST UPDATE DATE:  10/09/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |
|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  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE                              |
|                                                                              |
| "At 1518 hours on October 9, 2002 Indian Point Unit 2 commenced a controlled |
| shutdown per T/S 3.0.1.  T/S 3.0.1 was entered because Emergency Diesel      |
| Generators (EDG) 21 and 23 were declared inoperable.  EDG 23 was declared    |
| inoperable at 2152 hours on October 8, 2002 due to failure of monthly test.  |
| EDG 21 was declared inoperable at 1359 hours on October 9, 2002 due to       |
| indications of jacket water in the lube oil system.  EDG 23 was declared     |
| operable at 1635 hours on October 9, 2002 following corrective actions and   |
| testing at which time T/S 3.0.1 was exited. They think EDG 21 may have a     |
| cracked engine head.  The reactor power reduction was stopped at 97 percent, |
| but the are planning to return to 100%.   The to the Public Service          |
| Commission was informed of the reason for the downpower at 1610 hours on     |
| October 9, 2002."                                                            |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39265       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 10/10/2002|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 00:20[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        10/10/2002|
+------------------------------------------------+EVENT TIME:        00:08[EDT]|
| NRC NOTIFIED BY:  ROBERT BOESCH                |LAST UPDATE DATE:  10/10/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN WHITE           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN DUE TO FAILURE TO MEET 2 OFFSITE POWER SUPPLIES  |
|                                                                              |
| "Susquehanna Unit 1 initiated a Technical Specification required shutdown    |
| due to failure to meet LCO 3.8.1 Action A.3 and the Notice of Enforcement    |
| Discretion (Docket No. 50-387), for operating with one inoperable offsite    |
| power supply. The offsite power supply was originally lost due to a          |
| Transformer failure on 10/3/02 at 0230 est. The NOED allowed Unit One to     |
| continue operation until 10/1 0/02 at 0230. The shutdown requirements of LCO |
| 3.8.1 Action F (Mode 3 within 12 hours and Mode 4 within 36 hours) are being |
| implemented. It has been determined that replacement activities of the       |
| transformer will not be completed in time to meet the NOED, and therefore    |
| shutdown of unit 1 has been initiated as of 0008.                            |
|                                                                              |
| "This event is a Technical Specification required shutdown, and is           |
| reportable as a four hour ENS Notification under 10 CFR 50.72(b)(2)(I)."     |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector.                        |
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