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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Other Nuclear Material |Event Number: 37062 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37063 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37064 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37065 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37066 |
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| 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 |
| | |
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EVENT TEXT
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| 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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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021