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Event Notification Report for December 31, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/28/2001 - 12/31/2001

                              ** EVENT NUMBERS **

38587  38598  38599  
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|Hospital                                         |Event Number:   38587       |
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| REP ORG:  PARK VIEW HOSPITAL                   |NOTIFICATION DATE: 12/20/2001|
|LICENSEE:  PARK VIEW HOSPITAL                   |NOTIFICATION TIME: 11:09[EST]|
|    CITY:  FT. WAYNE                REGION:  3  |EVENT DATE:        12/19/2001|
|  COUNTY:                            STATE:  IN |EVENT TIME:             [CST]|
|LICENSE#:  13-01284-02           AGREEMENT:  N  |LAST UPDATE DATE:  12/28/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MONTE PHILLIPS       R3      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOHN AGNEW                   |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| POSSIBLE MEDICAL MISADMINISTRATIONS COULD HAVE OCCURRED DURING
THERAPEUTIC   |
| TREATMENTS IN 1998.                                                          |
|                                                                              |
| A radiopharmacy (Spectrum Co.) supplied the hospital with incorrectly        |
| calibrated doses of samarium-153 which were used in 1998 during three        |
| (04/15/98, 06/03/98, and 06/10/98) therapeutic treatments for bone pain.     |
| The supplier believes the doses may be 20-30% less than what was calculated. |
| They are currently performing calculations to determine what the doses were  |
| and have already reported this problem to the NRC.   The hospital was        |
| notified on 12/19/01 of this calculation error.                              |
|                                                                              |
| ***** UPDATE RECEIVED AT 1437 EST ON 12/28/01 FROM JOHN AGNEW TO LEIGH       |
| TROCINE *****                                                                |
|                                                                              |
| The licensee is updating this event notification to provide the actual doses |
| received during the treatments in question.                                  |
|                                                                              |
| The written directive for the 04/15/98 treatment was 90 millicuries of       |
| samarium-153, and the radiopharmacy recalculated the actual dose to be 67.18 |
| millicuries.  The written directive for the 06/03/98 treatment was 54        |
| millicuries of samarium-153, and the radiopharmacy recalculated the actual   |
| dose to be 42.44 millicuries.  The written directive for the 06/10/98        |
| treatment was 54 millicuries of samarium-153, and the radiopharmacy          |
| recalculated the actual dose to be 41.14 millicuries.                        |
|                                                                              |
| The NRC operations officer notified the R3DO (Brent Clayton) and NMSS EO     |
| (Fred Brown).                                                                |
|                                                                              |
| (Call the NRC operations officer to obtain contact telephone numbers for     |
| John Agnew and for Spectrum.)                                                |
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|Power Reactor                                    |Event Number:   38598       |
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| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 12/27/2001|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 16:03[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/27/2001|
+------------------------------------------------+EVENT TIME:        13:21[EST]|
| NRC NOTIFIED BY:  DOUG PERRY                   |LAST UPDATE DATE:  12/29/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR SCRAM AFTER TWO RECIRCULATION MOTOR-GENERATOR (MG) SETS
TRIPPED      |
| DURING THE PERFORMANCE OF ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
LOGIC   |
| TESTING                                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "While performing ATWS logic testing, both [the] 'A' [and] 'B'               |
| [recirculation] MG sets tripped, and the reactor was scrammed.  The cause of |
| the scram is being determined at this time.  All control rods fully inserted |
| on the scram.  All safety systems functioned properly during the transient.  |
| The plant is in the process of being maneuvered to Cold Shutdown."           |
|                                                                              |
| The licensee stated that the main steam isolation valves remained open and   |
| that none of the safety relief valves lifted.  In addition, there were no    |
| emergency core cooling system actuations, and none were required.  The       |
| reported engineered safety feature actuation was the actuation of the        |
| reactor protection system.                                                   |
|                                                                              |
| The unit is currently stable in Hot Shutdown.  Normal condensate and         |
| feedwater is being utilized to supply water to the reactor vessel, and the   |
| condenser is being utilized as a heat sink.  Containment parameters are      |
| normal, offsite power is available, and the electrical grid is stable.  The  |
| emergency diesel generators and engineered safety feature systems are        |
| available if needed.                                                         |
|                                                                              |
| The licensee stated that the ATWS logic test procedure was not new and that  |
| it had been performed on several occasions in the past.  The ATWS logic test |
| was successfully completed for the 'A' side earlier today, and the plant     |
| transient occurred during the performance of the ATWS logic test for the 'B' |
| side.  The cause of the recirculation MG set trips is currently under        |
| investigation.                                                               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATED AT 0023 ON 12/29/01 BY ERIC OLSON TO FANGIE JONES * * *        |
|                                                                              |
| The licensee reported the cause of the scram as Average Power Range (APR)    |
| Hi-Hi trip caused by a flow control trip reference card signal from the low  |
| flow due the trip of both recirc pumps.                                      |
|                                                                              |
| The NRC Resident Inspector has been informed by the licensee.  The R1DO      |
| (Michele Evans) has been informed.                                           |
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|Power Reactor                                    |Event Number:   38599       |
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 12/31/2001|
|    UNIT:  [] [2] []                 STATE:  NJ |NOTIFICATION TIME: 02:00[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/31/2001|
+------------------------------------------------+EVENT TIME:        00:10[EST]|
| NRC NOTIFIED BY:  S. SAUER                     |LAST UPDATE DATE:  12/31/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|ACCS 50.72(b)(2)(iv)(A)  ECCS INJECTION         |                             |
|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     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR TRIP AND SAFETY INJECTION DUE TO SPRAY VALVE FAILING OPEN            |
|                                                                              |
| The unit experienced a reactor trip and safety injection as a result of a    |
| pressurizer spray valve (2PS3) failing open.  This caused a reactor trip on  |
| Overtemperature DeltaT and a safety injection on low reactor coolant system  |
| pressure.  All emergency equipment responded properly, all safety injection  |
| pumps started and all control rods fully inserted.  The emergency diesels    |
| started, but did not load as designed.  The auxiliary feedwater pumps        |
| started on low steam generator level.  The pressurizer spray valve closed    |
| when the valve's operating air was isolated.                                 |
|                                                                              |
| The unit is stable in Mode 3 (Hot Standby) at normal temperature and         |
| pressure.  Auxiliary feedwater and steam dumps are in use to maintain steam  |
| generator level and remove excess heat.  An investigation of the failure is  |
| underway.                                                                    |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector and the local      |
| Township.                                                                    |
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