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Event Notification Report for October 11, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/10/2001 - 10/11/2001

                              ** EVENT NUMBERS **

38362  38366  38370  38371  38372  38373  38375  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38362       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 10/07/2001|
|    UNIT:  [] [2] []                 STATE:  MI |NOTIFICATION TIME: 13:02[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/07/2001|
+------------------------------------------------+EVENT TIME:        09:50[EDT]|
| NRC NOTIFIED BY:  STEVE CHERBA                 |LAST UPDATE DATE:  10/10/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |
|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       8        Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED REACTOR TRIP DURING PLANT STARTUP OPERATIONS                      |
|                                                                              |
| ". . . . This event occurred at 0950 hours this morning (10-7-01). Currently |
| the Unit is in Mode 3 with all systems normal. At the time of the trip the   |
| unit was at approximately 8 % power (by RCS AT indication, about 6 to 7 % on |
| Power Range Nuclear Instrumentation) in power ascension and was just         |
| preparing to roll the main turbine.                                          |
|                                                                              |
| "RCS Tavg was noted to decrease below the normal 547 F no-load post-trip    |
| value to about 535 F by the Reactor Operator monitoring the temperature. At |
| the time of the trip one main feedwater pump was supplying the Steam         |
| Generators (SG), with low-flow feedwater pre-heating in service. Main        |
| feedwater isolated on the trip with the SGs being supplied post trip by the  |
| motor driven Auxiliary Feedwater (AFW) Pumps. The RCS cooldown was           |
| attributed to the #4 SG AFW flow control valve not closing as expected on    |
| high flow thus allowing too much flow to #4 SG, as well as steam that was    |
| still being supplied to low flow feedwater preheating. Operator actions      |
| taken in response to the cooldown were to close the main steam stop valves,  |
| and review AFW valve positions so as to limit steam flow from, and feed flow |
| to, the SGs. These actions were completed by 0959 hours, and were sufficient |
| to maintain temperature control. RCS temperature shortly recovered to 547 F |
| at about 1032 hours, 10-7-01. No other significant abnormalities were noted, |
| pressurizer pressure decreased in response to the temperature transient, and |
| the subsequent RCS shrink caused RCS letdown to isolate on low pressurizer   |
| level. The plant is presently stable in Mode 3. No other RPS or SI setpoints |
| were exceeded due to the trip and subsequent temperature transient. All      |
| other systems and equipment functioned normally.                             |
|                                                                              |
| "The initiating RPS signal was a high Power Range Nuclear Instrument Rate    |
| Trip on 2 out of 4 channels. Cause of this rate trip is not definitively     |
| known at this time, rapid event teams to investigate and evaluate the trip   |
| have been initiated. Suspected cause is a Rod Control System problem."       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE 0353EDT ON 10/10/01 FROM DALE TURINETTI TO S. SANDIN * * *      |
|                                                                              |
| The following information was received as an update to this report:          |
|                                                                              |
| "The cause of the Unit 2 reactor trip was a negative rate trip as a result   |
| of a loss of Rod Control Motor Generator set voltage. The loss of voltage    |
| was attributed to a failed open resistor on the North motor generator set    |
| which caused a loss of voltage regulation. It is believed this loss of       |
| voltage caused the north motor generator set to act as a load; and the south |
| motor generator set could not maintain the output voltage. The reduction in  |
| voltage caused a collapse of field and the subsequent release of control     |
| rods and resultant negative rate trip.                                       |
|                                                                              |
| "The motor generator set resistors have been replaced and associated relays  |
| have been tested to ensure proper operation of the motor generator sets.     |
| Plant power ascension is in progress with the unit in mode 1 and at 25%."    |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R3DO(Parker).    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38366       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 10/09/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 12:22[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        10/09/2001|
+------------------------------------------------+EVENT TIME:        11:30[EDT]|
| NRC NOTIFIED BY:  JOHN SCHORK                  |LAST UPDATE DATE:  10/10/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CLIFF ANDERSON       R1      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Intermediate Shut|0        Intermediate Shut|
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LANCASTER COUNTY EMERGENCY SIRENS WERE FOUND INOPERABLE                      |
|                                                                              |
| "At 11:30 AM on 10/9/01, TMI determined that the apparent inoperability of   |
| emergency sirens in Lancaster County, Pennsylvania for approximately 3 days  |
| met the criteria set forth in NUREG 1022, Rev. 2 for a major loss of         |
| emergency offsite communications capability and that an immediate 8 hour     |
| notification in accordance with 10 CFR 50.72(b)(3)(xiii) was required.       |
|                                                                              |
| "At approximately 8:55 am on Tuesday, October 9, 2001 the emergency sirens   |
| in Lancaster County were inadvertently activated during routine maintenance  |
| by Capitol Area Communications, the siren vendor. During the weekly          |
| evaluation of system electronics on Tuesday, October 9, 2001, Capitol Area   |
| Communications had discovered an anomaly with the system communications with |
| Lancaster County. Capitol Area Communications called Lancaster County and it |
| was found that apparently the transmitter for Lancaster County had been      |
| incorrectly left turned off following recent maintenance performed on        |
| Saturday, October 6, 2001 that occurred in the vicinity of the transmitter.  |
|                                                                              |
| "The transmitter was turned back on at approximately 8:55 am on Tuesday,     |
| October 9, 2001. When the transmitter was turned on, a signal that had been  |
| sent on Saturday, October 6, 2001 for the monthly Saturday test of the       |
| sirens that had been received but not acted upon, was acted upon by the      |
| transmitter which then activated the sirens. The sirens were silenced upon   |
| recognition of the inadvertent actuation. Lancaster County is notifying      |
| local media of the cause of the inadvertent siren actuation.                 |
|                                                                              |
| "Subsequent discussions between Exelon Emergency Management personnel and    |
| the siren vendor determined that the sirens for Lancaster County had         |
| apparently been inoperable from sometime on Saturday, October 6 until today, |
| Tuesday, October 9.                                                          |
|                                                                              |
| "The sirens in Lancaster County were reactivated when the transmitter [was   |
| turned] back on.                                                             |
|                                                                              |
| "The Lancaster County 911 dispatcher number 41 called the TMI Control Room   |
| at approximately 9:00 AM. The Control notified a duty public information     |
| representative of the siren malfunction. The duty Public Information         |
| Representative spoke with Lancaster County Emergency Management at 9:13 am   |
| who confirmed the information received from the 911 dispatcher.              |
| Subsequently, at 9:15 am Exelon emergency management reconfirmed the         |
| information received.                                                        |
|                                                                              |
| "The site Sr. Resident Inspector has been informed of the event and the 8    |
| hour report. TMI Communications contacted the Lancaster County Commissioners |
| and PEMA to inform them of the event."                                       |
|                                                                              |
| * * * UPDATE 1423 10/10/2001 FROM SCHORK TAKEN BY STRANSKY * * *             |
|                                                                              |
| "This is a revision of the initial 8 hour notification made by TMI-1 per     |
| Event Notification 38366 on October 9, 2001 at 1222 hours. The revised       |
| notification is being submitted to document that the sirens in question were |
| out of service for approximately 4 days instead of the initial report of 3   |
| days and that a contributing cause to the event may be the software that is  |
| used in performing the test.                                                 |
|                                                                              |
| "Additional discussions between TMI Emergency Preparedness, Exelon Emergency |
| Preparedness, Lancaster County Emergency Management and Capitol Area         |
| Communications that took place on Wednesday, October 10, 2001 determined     |
| that the siren transmitter was out of service from Friday, October 5 to      |
| Tuesday, October 9. In addition, a functional test of the computer software  |
| used to perform the weekly test in Lancaster County found that the software  |
| did not detect a failure of the sirens to actuate when the transmitter is    |
| de-energized. The software does detect siren failures when the transmitter   |
| is energized. Exelon Emergency Preparedness is contacting the software       |
| vendor to obtain additional information. The software in question was        |
| provided by AmerGen to the 5 risk counties for Three Mile Island Nuclear     |
| Power Station."                                                              |
|                                                                              |
| The NRC resident inspector has been informed of this update by the licensee. |
| Notified R1 IRC.                                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38370       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 10/10/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 08:44[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/10/2001|
+------------------------------------------------+EVENT TIME:        02:53[EDT]|
| NRC NOTIFIED BY:  CHRIS SERATA                 |LAST UPDATE DATE:  10/10/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|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          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC RPS ACTUATION ON LOW REACTOR VESSEL WATER LEVEL FOLLOWING UNIT     |
| SHUTDOWN                                                                     |
|                                                                              |
| "Following the shutdown of Hope Creek Generating Station at the beginning of |
| the 10th Refueling Outage, a subsequent low reactor water level condition    |
| occurred which resulted in actuation of the Reactor Protection System (RPS). |
| The low level occurred when reactor depressurization was terminated. The     |
| unit was in Hot Shutdown at the time of the RPS actuation with all control   |
| rods fully inserted.                                                         |
|                                                                              |
| "Cooldown to Operational Condition 4 is in progress."                        |
|                                                                              |
|                                                                              |
| The licensee will inform the Lower Alloways Creek Township and the NRC       |
| resident inspector.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38371       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 10/10/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 08:44[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/10/2001|
+------------------------------------------------+EVENT TIME:        03:32[EDT]|
| NRC NOTIFIED BY:  CHRIS SERATA                 |LAST UPDATE DATE:  10/10/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |                             |
|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        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RCS PRESSURE BOUNDARY LEAKAGE IDENTIFIED DURING CONTAINMENT WALK DOWN        |
|                                                                              |
| "During a Primary Containment walk down at the beginning of the Hope Creek   |
| 10th Refueling Outage, inspection crews identified a cracked weld on the 'A' |
| Reactor Recirculation Loop elbow tap instrument piping, which is part of the |
| Reactor Coolant Pressure Boundary. The cracked weld is located where a 1"    |
| tap connects to the 28" recirculation loop piping, and constitutes a part of |
| the Reactor Coolant Pressure Boundary. The unit was in Hot Shutdown          |
| Operational Condition 3 at the time of discovery.                            |
|                                                                              |
| "Technical Specification LCO 3.4.3.2.a has been entered due to leakage from  |
| the Reactor Coolant Pressure Boundary, which requires the unit be in Cold    |
| Shutdown by 03:32am on October 11, 2001.  Cooldown to Operational Condition  |
| 4 is in progress.                                                            |
|                                                                              |
| "PSEG Nuclear is developing plans to repair the leak."                       |
|                                                                              |
| The licensee described the leak as a fine spray which is much less than the  |
| 10gpm averaged over a 10 minute period required to declare an Unusual Event  |
| (ECG 2.1.1a, 2.1.1b).                                                        |
|                                                                              |
| The licensee will inform the Lower Alloways Creek Township and the NRC       |
| resident inspector.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38372       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 10/10/2001|
|LICENSEE:  LEIGHTON AND ASSOCIATES              |NOTIFICATION TIME: 11:19[EDT]|
|    CITY:  IRVINE                   REGION:  4  |EVENT DATE:        10/08/2001|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:  3109-30               AGREEMENT:  Y  |LAST UPDATE DATE:  10/10/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA HOWELL         R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KENT PRENDERGAST             |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| "Licensee reported that a Troxler 3440 portable gauge containing 10 mCi of   |
| cesium-137 and 50 mCi of americium-241:beryllium, in sealed sources, was     |
| stolen from one of their technician's pick-up while being kept overnight at  |
| the technician's home in Hemet. The gauge was in its transport case, locked  |
| down in the bed of the vehicle with a 'shell.'                               |
|                                                                              |
| "The gauge was stolen sometime after being parked at the technician' s home  |
| on the evening of 10-8-01.                                                   |
|                                                                              |
| "The stolen gauge was a Troxler 3440, S/N 14409."                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38373       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 10/10/2001|
|    UNIT:  [] [2] []                 STATE:  AZ |NOTIFICATION TIME: 11:23[EDT]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        10/10/2001|
+------------------------------------------------+EVENT TIME:        07:45[MST]|
| NRC NOTIFIED BY:  DAN MARKS                    |LAST UPDATE DATE:  10/10/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LINDA HOWELL         R4      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |75       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN BASED ON ASSUMED CEA          |
| DEGRADATION                                                                  |
|                                                                              |
| "The following event description is based on information currently           |
| available. If through subsequent reviews of this event, additional           |
| information is identified that is pertinent to this event or alters the      |
| information being provided at this time, a follow-up notification will be    |
| made via the ENS or under the reporting requirements of 10CFR50.73.          |
|                                                                              |
| "On October 10, 2001, at approximately 07:45 MST, Palo Verde Nuclear         |
| Generating Station (PVNGS) Unit 2 commenced a reactor shutdown required by   |
| Technical Specification 3.0.3.                                               |
|                                                                              |
| "CEA degradation was observed during refueling of PVNGS Unit 3 and is        |
| assumed to be transportable to Unit 2. As discussed in the Technical         |
| Specification 3.1.5 Bases, mechanical failures may cause a CEA to become     |
| inoperable. There were no reactivity anomalies in Unit 2 (or Unit 3)         |
| indicating CEA degradation prior to this discovery. The condition is not     |
| transportable to PVNGS Unit 1 CEAs because they were replaced during its     |
| last refueling outage.                                                       |
|                                                                              |
| "Preliminary investigation indicates the cause to be aging.                  |
|                                                                              |
| "Limiting Condition for Operability (LCO) 3.1 .5 requires 'All full length   |
| CEAs shall be OPERABLE..'    No associated action in Technical Specification |
| 3.1.5 applies to the CEA degradation, therefore Unit 2 entered LCO 3.0.3.    |
|                                                                              |
| "No ESF actuations occurred and none were required. There were no            |
| structures, systems, or components that were inoperable at the time of       |
| discovery that contributed to this condition. There were no failures that    |
| rendered a train of a safety system inoperable and no failures of components |
| with multiple functions were involved. The event did not result in the       |
| release of radioactivity to the environment and did not adversely affect the |
| safe operation of the plant or health and safety of the public.              |
|                                                                              |
| "The NRC Resident Inspector has been notified."                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38375       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 10/10/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 15:38[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        10/10/2001|
+------------------------------------------------+EVENT TIME:        12:30[EDT]|
| NRC NOTIFIED BY:  J. GROFF                     |LAST UPDATE DATE:  10/10/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHAEL PARKER       R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI INOPERABLE                                                              |
|                                                                              |
| "On 10/10/01 at 12:30, while performing surveillance 24.202.01 'HPCI Pump    |
| Time Response and Operability Test at 1025 psi', HPCI pump flow reached 5000 |
| gpm in 35 seconds (<29 seconds is acceptance criteria). HPCI was declared    |
| INOPERABLE due to the surveillance failure. Plant personnel are evaluating   |
| trend data to determine the cause of the failure.                            |
|                                                                              |
| "All other ECCS systems and RCIC are OPERABLE. This is being reported under  |
| 10CFR50.72(b)(3)(v)(D)."                                                     |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+