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Event Notification Report for November 2, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/01/2001 - 11/02/2001

                              ** EVENT NUMBERS **

38435  38453  38454  38457  
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|Power Reactor                                    |Event Number:   38435       |
+------------------------------------------------------------------------------+
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| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 10/28/2001|
|    UNIT:  [1] [] []                 STATE:  VA |NOTIFICATION TIME: 01:05[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/28/2001|
+------------------------------------------------+EVENT TIME:        00:15[EDT]|
| NRC NOTIFIED BY:  ALLEN HARROW                 |LAST UPDATE DATE:  11/02/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BOB HAAG, REGION 2   IRC     |
|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| DISCOVERY OF APPARENT THROUGH-WALL INDICATIONS ON CONTROL ROD DRIVE    
     |
| MECHANISM PENETRATIONS                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Following shutdown for a scheduled refueling outage, Surry Unit 1 performed |
| a visual inspection of the reactor vessel control rod drive mechanism (CRDM) |
| penetrations per NRC Bulletin 2001-01."                                      |
|                                                                              |
| "At approximately 0015 on October 28, 2001, apparent through-wall            |
| indications were identified on CRDM penetrations 27 and 40.  The inspection  |
| is not yet complete.  This condition did not pose a significant safety risk  |
| during plant operation.  This is being reported as a non-emergency (8-hour   |
| report in accordance with 10 CFR 50.72(b)(3)(ii)(A) and                      |
| 50.73(a)(2)(ii)(A)."                                                         |
|                                                                              |
| The licensee stated that the unit is currently defueled.                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE ON 11/2/01 @ 0338 BY HILBERT-SEMMES TO GOULD * * *   UPDATE     |
|                                                                              |
| Following shutdown for a scheduled refueling outage, Surry Unit 1 performed  |
| a visual inspection of the reactor vessel Control Rod Drive Mechanism (CRDM) |
| penetrations per NRC Bulletin 2001-01.                                       |
|                                                                              |
| At approximately 0220 hours on November 2, 2001, additional indications were |
| identified as having flaws that are not acceptable under ASME Section XI     |
| IWB-3600 on penetrations 65, 47, and 69.  Two previously identified          |
| indications were previously reported in this event. The inspection of all    |
| CRDM penetrations is now complete with disposition of one penetration still  |
| underway.  This condition did not pose a significant safety risk during      |
| plant operation.  This is being reported as an update.                       |
|                                                                              |
| The NRC Resident Inspector was notified.   The Reg 2 IRC Manager was         |
| notified.                                                                    |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38453       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 11/01/2001|
|    UNIT:  [1] [] []                 STATE:  AL |NOTIFICATION TIME: 09:47[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/31/2001|
+------------------------------------------------+EVENT TIME:             [CST]|
| NRC NOTIFIED BY:  HAWKINS                      |LAST UPDATE DATE:  11/01/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R2 IRC TEAM MANAGER  R2      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTROL RODS DID NOT FULLY INSERT DURING CONTROL ROD TEST                    |
|                                                                              |
| On October 31 and November 1, 2001 following reactor vessel assembly and     |
| heat up, control rod drop testing was performed in mode 3.  Rods N-9 and C-9 |
| did not fully insert into the dashpot region (24 steps) following            |
| operability and trip testing.   Rod J-13 exhibited similar characteristics   |
| following operability and trip testing but shortly after trip testing it     |
| fully inserted.   Four other rods fully inserted but were slower than normal |
| in the dashpot region.  All other control rods tested fully acceptable.  The |
| Unit is currently cooling down and plans are under way to replace            |
| unacceptable control rods as necessary.  The Unit has remained borated above |
| the all rods out critical boron concentration since core reload and adequate |
| SDM exits.                                                                   |
|                                                                              |
| On October 06, 2001 Farley Unit 1 commenced a normal Unit shutdown to start  |
| its 17th refueling outage.   All control rods were fully inserted with no    |
| problems.  During insert and control rod changeout in the Unit 1 fuel pool   |
| several control rods not scheduled to go back into the core experienced      |
| binding in older fuel assemblies that prevented the rods from fully          |
| inserting in the dashpot region of assemblies.  Upon investigation of the    |
| old control rods scheduled to be replaced axial cracks were observed by      |
| visual exmination in several assemblies near the rod ends but above the rod  |
| tips.  This resulted in an inspection program for 18 older control rods      |
| scheduled to go back into the core to confirm the acceptability for          |
| continued use in cycle 18.  Visual inspection and drag testing was performed |
| in the Unit 1 Spent Fuel.   Westinghouse reviewed the test results and       |
| confirmed the acceptability of 18 control rods for Cycle 18 use.             |
|                                                                              |
| The NRC Resident was notified.                                               |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   38454       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ST BARNABAS MEDICAL CENTER           |NOTIFICATION DATE: 11/01/2001|
|LICENSEE:  ST BARNABAS MEDICAL CENTER           |NOTIFICATION TIME: 10:36[EST]|
|    CITY:  LIVINGSTON               REGION:  1  |EVENT DATE:        10/26/2001|
|  COUNTY:                            STATE:  NJ |EVENT TIME:             [EST]|
|LICENSE#:  29-01608-03           AGREEMENT:  N  |LAST UPDATE DATE:  11/01/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |R1 IRC TEAM MANAGER  R1      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GARELICK                     |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION DURING THERAPEUTIC TREATMENT REPORTED BY ST 
      |
| BARNABAS MEDICAL CENTER                                                      |
|                                                                              |
| A patient undergoing the third therapeutic treatment received a dose to an   |
| unintended treatment site due to an incorrect step size on a High Rate       |
| Remote After Loader which was used in the treatment.  This was the result of |
| human error.   It was determined there will be no medical implications and   |
| the patient will be notified.                                                |
+------------------------------------------------------------------------------+
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38457       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 11/01/2001|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 15:13[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        11/01/2001|
+------------------------------------------------+EVENT TIME:        12:30[CST]|
| NRC NOTIFIED BY:  ALAN SMITH                   |LAST UPDATE DATE:  11/01/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BLAIR SPITZBERG      R4      |
|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     A/R        Y       22       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DURING CEA TROUBLESHOOTING FOR REASONS
UNKNOWN        |
|                                                                              |
| "While operating at full power at approximately 1010 CST on 11/01/2001,      |
| Control Element Assembly (CEA) 43 dropped into the core for unknown reasons. |
| Reduction of reactor power began at approximately 1017.  With reactor power  |
| stable at approximately 22 percent, troubleshooting of the cause of the      |
| CEA-43 drop was in progress at approximately 1230 CST when an automatic      |
| reactor trip occurred.  The reason for the trip is unknown.  Plant response  |
| to the trip was normal and uncomplicated.  All CEAs fully inserted.  There   |
| were no ESF system actuations. The plant is stable in Hot Standby (Mode 3)   |
| conditions with decay heat being removed via the Steam Generators to the     |
| Main Condenser.  No radiation releases occurred."                            |
|                                                                              |
| The licensee informed the state and NRC Resident Inspector.                  |
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