Event Notification Report for June 8, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/07/2000 - 06/08/2000

                              ** EVENT NUMBERS **

37062  37063  37064  37065  37066  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37062       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SOUTH COAST MEDICAL CENTER           |NOTIFICATION DATE: 06/06/2000|
|LICENSEE:  SOUTH COAST MEDICAL CENTER           |NOTIFICATION TIME: 19:04[EDT]|
|    CITY:  LAGUNA BEACH             REGION:  4  |EVENT DATE:        06/06/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:        14:30[PDT]|
|LICENSE#:  0920-30               AGREEMENT:  Y  |LAST UPDATE DATE:  06/07/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |WILLIAM BRACH        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOSE BRUNO                   |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| WIPE TEST OF PACKAGE EXTERIOR RESULTED IN A COUNT LEVEL OF 4442 DPM          |
|                                                                              |
| A package containing technetium - 99m (NaTcO4) delivered by NYCOMED Amersham |
| to South Coast Medical Center was found to have surface contamination level  |
| above the 2.2 DPM per square centimeter limit.  The wipe of the outer        |
| surface of the package (metal canister) was placed in a well counter and the |
| counter indicated the that total count on the  wipe was 4442 +/-149 DPM.     |
| The outer dimensions of the metal canister are 15 centimeters by 25          |
| centimeters by 29 centimeters. The licensee will contact NYCOMED Amersham    |
| located in Anaheim, CA, and ask them to pickup the package.  The package was |
| not opened.   Activity of the technetium-99m (NaTcO4) was originally 25      |
| millicuries and the quantity is 2.4838 milliliters.                          |
|                                                                              |
| * * * RETRACTION ON 06/07/00 AT 1152 ET BY JOSE BRUNO TAKEN BY MACKINNON * * |
| *                                                                            |
|                                                                              |
| The licensee is retracting this event because the surface contamination of   |
| the metal container in DPM per square centimeter is below the reportable     |
| limit of 2.2 DPM per square centimeter.  The surface area of the metal       |
| container was 2990 square centimeters and the count of the wipe was 4442     |
| DPM.  Therefore the average surface contamination per square centimeter is   |
| 1.49 DPM which is below the reportable limit of 2.2 DPM per square           |
| centimeter. NMSS EO (Josie Piccone)  & R4DO (John Pellet) notified.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37063       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 06/07/2000|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 01:32[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        06/06/2000|
+------------------------------------------------+EVENT TIME:        23:10[CDT]|
| NRC NOTIFIED BY:  RUITER                       |LAST UPDATE DATE:  06/07/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       35       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT HAD A MANUAL REACTOR TRIP FROM 35% POWER.                              |
|                                                                              |
| At 2243 on 06/06/2000 an alarm for high reactor coolant pump "A" bearing     |
| water temperature came in on the plant process computer.  At 2310 the        |
| reactor coolant pump "A" bearing water temperature exceeded 225�F and a      |
| manual reactor trip was initiated and the "A" reactor coolant pump was       |
| secured.  Following the reactor trip all three auxiliary feed water pumps    |
| started and equipment response was as expected.  All rods fully inserted and |
| no safety relief valves lifted.  Currently the turbine driven aux feed is    |
| secured, but the motor driven aux feed is still operating.  They are         |
| investigating if the cause was a temperature indicating problem or a bearing |
| failure.                                                                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37064       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 06/07/2000|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 15:36[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        06/07/2000|
+------------------------------------------------+EVENT TIME:        13:42[CDT]|
| NRC NOTIFIED BY:  WEAVER                       |LAST UPDATE DATE:  06/07/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) BREAKER OPENED CAUSING A LOSS OF      |
| INPUTS TO THE CONTROL ROOM TERMINAL.                                         |
|                                                                              |
| CONTROL ROOM EXPERIENCED A LOSS OF SPDS DUE TO A BREAKER TRIPPING WHICH      |
| SUPPLIES POWER TO THE CONTROL ROOM SPDS TERMINAL.  INVESTIGATION OF WHY THE  |
| BREAKER TRIPPED AND RESET IS UNDERWAY.  SHORTLY BEFORE THE BREAKER TRIPPED   |
| A CARPET CLEANER WAS ENERGIZED IN THE CONTROL ROOM.                          |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.   |
|                                                                              |
| * * * UPDATE ON 06/07/00 AT 1728 ET BY WEAVER TAKEN BY MACKINNON * * *       |
|                                                                              |
| SPDS WAS RETURNED TO SERVICE AT 1608 CDT. IT WAS DISCOVERED THAT A FUSE HAD  |
| BLOWN INSTEAD OF A BREAKER OPENING.  THE FUSE WAS REPLACED AND THE SPDS WAS  |
| RETURNED TO SERVICE.  R4DO (PELLET) NOTIFIED.                                |
|                                                                              |
| THE  NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE.     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37065       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 06/07/2000|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 19:28[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        06/07/2000|
+------------------------------------------------+EVENT TIME:        17:55[EDT]|
| NRC NOTIFIED BY:  LISA HILBERT-SEMMES          |LAST UPDATE DATE:  06/07/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES OGLE         R2      |
|10 CFR SECTION:                                 |WILLIAM BRACH        NMSS    |
|ISFS 72.75               SPENT FUEL CASK EVENT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DEFECT IN A SPENT FUEL STORAGE CASK STRUCTURE                                |
|                                                                              |
| At 1755 hours, as a result of troubleshooting due to a low pressure alarm at |
| the Surry ISFSI Facility, it was determined that a leak existed in the lid   |
| seal system on Dry Storage Cask #2-3 which exceeds the ISFSI Tech Spec limit |
| of 1E-5mbar-l/sec. This is a TN-32.01 cask that was placed at the Surry      |
| ISFSI Facility, pad #2 in 1996. It has been verified that the cask's         |
| overpressure monitoring system does not leak and continued to maintain a     |
| pressure greater than the cask's internal fuel cavity pressure.  Therefore,  |
| it was not possible for any release of potentially radioactive material as a |
| result of a seal failure. The cask was returned from the ISFSI pad to the    |
| station on Friday, June 2, 2000 due to the low pressure alarm. Radiation     |
| levels at the cask prior to transport to the station were normal. Additional |
| tests are being conducted to determine which seal (either inner or outer) is |
| affected. Investigation is on going for determining the cause and required   |
| corrective actions for this issue. Both Unit 1 and Unit 2 are currently at   |
| 100% power. Pursuant to 10CFR72.75(b)(2), this is being reported as a defect |
| in a spent fuel storage cask structure, system, or component that is         |
| important to safety.                                                         |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37066       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 06/07/2000|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 20:25[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        06/07/2000|
+------------------------------------------------+EVENT TIME:        20:00[EDT]|
| NRC NOTIFIED BY:  MATUSZEWSKI                  |LAST UPDATE DATE:  06/07/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES OGLE         R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|4     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AT 2000 HOURS IT WAS NOTED THAT THE EMERGENCY RESPONSE DATA ACQUISITION      |
| DISPLAY SYSTEM (ERDADS) DATA LINK TO THE EMERGENCY RESPONSE DATA SYSTEM WAS  |
| DOWN (LOCKED UP).  PERSONNEL HAVE BEEN CALLED TO COME IN AND REPAIR THE      |
| ERDADS SYSTEM.                                                               |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.   |
|                                                                              |
| * * * UPDATE ON 06/07/00 AT 2159 ET BY FREW TAKEN BY MACKINNON * * *         |
|                                                                              |
| ERDADS RETURNED TO SERVICE AT 2157 ET (ERDADS HAD LOCKED UP).                |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE.      |
+------------------------------------------------------------------------------+


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