Event Notification Report for March 3, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/28/2003 - 03/03/2003
** EVENT NUMBERS **
39627 39628 39629 39630 39631
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|Power Reactor |Event Number: 39627 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 02/28/2003|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 14:10[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/28/2003|
+------------------------------------------------+EVENT TIME: 08:57[CST]|
| NRC NOTIFIED BY: PETER DONAHUE |LAST UPDATE DATE: 02/28/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
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EVENT TEXT
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| LESS THAN THE REQUIRED NUMBER OF OPERABLE EMERGENCY DIESEL GENERATORS |
| |
| "While the plant was in cold shutdown, the division number 2 onsite |
| emergency power (diesel generator) was made inoperable when it was |
| discovered that the time delay relay, which energizes to cause the |
| associated room cooling system to start when the diesel generator |
| automatically initiates or the temperature in the room reaches 104 degrees |
| F, was not replaced before exceeding it's analyzed service life. The |
| division number 1 onsite emergency power (diesel generator) was already |
| inoperable when the fuel oil transfer pump flow was found to be less than |
| required while performing a technical specification surveillance test. |
| |
| "Technical Specification Limiting Condition of Operation (LCO) [3.8.2] for |
| AC Sources during shutdown was entered. This LCO is required to be entered |
| when one diesel generator is not capable of supplying one division of the |
| onsite Class 1E AC electrical power distribution subsystem(s) to support |
| equipment required to be operable. The following actions were immediately |
| taken in accordance with this LCO and will remain in place until the LCO can |
| be met: |
| |
| 1. Core alterations are not allowed. |
| 2. Movement of irradiated fuel assemblies iii secondary containment is not |
| allowed. |
| 3. Operations with the potential to drain the reactor vessel are not |
| allowed. |
| 4. Replacement of the subject relay was initiated. |
| |
| "No fuel movement, core alterations or operations with the potential to |
| drain the reactor vessel were in progress. |
| |
| "All offsite power sources are available and operable. No maintenance will |
| be conducted which could potentially affect the availability of these |
| offsite sources or the associated distribution systems." |
| |
| The licensee has notified the NRC Resident Inspector. |
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|Hospital |Event Number: 39628 |
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| REP ORG: THOMAS JEFFERSON UNIV HOSPITAL |NOTIFICATION DATE: 02/28/2003|
|LICENSEE: THOMAS JEFFERSON UNIV HOSPITAL |NOTIFICATION TIME: 15:52[EST]|
| CITY: PHILADELPHIA REGION: 1 |EVENT DATE: 01/28/2003|
| COUNTY: STATE: PA |EVENT TIME: 13:00[EST]|
|LICENSE#: 37-00148-06 AGREEMENT: N |LAST UPDATE DATE: 02/28/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN KINNEMAN R1 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOHN KEKLAK | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 1.3 MILLICURIES SULPHUR-35 SOURCE INADVERTENTLY DISCARDED AS REFUSE |
| |
| On 1/20/03 a package was delivered from PerkinElmer Lifesciences located in |
| Boston, MA to the Thomas Jefferson University Hospital. The package |
| included two (2) medical isotopes used in research; 1.3 millicuries |
| Sulphur-35 (Half-life 87.4 days) and 250 microcuries Tritiated Thymidine. |
| The package was shipped as excepted quantity not subject to external |
| labeling. A lab worker sometime between 1/23 and 1/24 discarded the package |
| containing the two sources as trash which was collected on 1/27 at |
| approximately 0500 hours and taken to the landfill. |
| |
| The licensee conducted interviews emphasizing prompt handling, good |
| communication and individual responsibility to prevent recurrence. |
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|Power Reactor |Event Number: 39629 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/01/2003|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 05:39[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/01/2003|
+------------------------------------------------+EVENT TIME: 01:54[CST]|
| NRC NOTIFIED BY: SCHAEFER |LAST UPDATE DATE: 03/01/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID GRAVES 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| REACTOR MANUALLY TRIPPED FROM 100% POWER |
| |
| The Operators manually trip the reactor from 100% power following a loss of |
| condensate flow in the secondary system. The cause is unknown and being |
| investigated. All rods fully inserted and no relief valves lifted. |
| However, the auxiliary feedwater and feedwater actuations were received |
| following the trip as expected. The reactor is in hot standby. |
| |
| |
| The NRC resident Inspector was notified. |
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|Power Reactor |Event Number: 39630 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/02/2003|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 10:43[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/02/2003|
+------------------------------------------------+EVENT TIME: 03:35[CST]|
| NRC NOTIFIED BY: LONG |LAST UPDATE DATE: 03/02/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT MEASURED LEAKAGE EXCEEDS THE ALLOWED LEAKAGE. |
| |
| During routine scheduled LLRT (Local Leak Rate Testing) of Penetration |
| X-214, HPCI (High Pressure Coolant Injection) Exhaust Discharge to the |
| Torus, leakage was unable to be quantified. Additionally, of the two |
| isolation check valves in the line, which one was leaking was unable to be |
| determined. As such, Primary Containment Allowed Leakage (La) is unable to |
| be verified to be less than allowed. |
| |
| The plant was in Mode 4 (Cold S/D) for a scheduled refueling outage with |
| temperature being maintained between 130 and 145 degrees Fahrenheit and |
| Primary Containment not required at the time of discovery. The plant will |
| remain in cold shutdown until repairs are completed. |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 39631 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 03/02/2003|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 16:00[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 03/02/2003|
+------------------------------------------------+EVENT TIME: 14:30[EST]|
| NRC NOTIFIED BY: CHARLES PIKE |LAST UPDATE DATE: 03/02/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| OFFSITE NOTIFICATION TO STATE AGENCY OF EXPIRED GREEN SEA TURTLE FOUND AT |
| BARRIER NET |
| |
| "NRC notification[is] being made due to state notification to [the] Florida |
| Wildlife Commission regarding a Green Sea Turtle found dead at barrier net |
| pursuant to 10 CFR 50.72(b)(2)(xi)." |
| |
| The turtle was found on the surface at the barrier net with no injuries or |
| abnormalities except for fresh cuts common for turtles coming through pipes. |
| The cause of death is unknown at this time. A necropsy is planned. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
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