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Event Notification Report for April 15, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/12/2002 - 04/15/2002

                              ** EVENT NUMBERS **

38707  38844  38848  38849  38850  38851  38852  38853  38854  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38707       |
+------------------------------------------------------------------------------+
                         
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| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/19/2002|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 01:27[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/18/2002|
+------------------------------------------------+EVENT TIME:        18:15[EST]|
| NRC NOTIFIED BY:  JAMES WITTER                 |LAST UPDATE DATE:  04/12/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES TRAPP          R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS INADVERTENTLY MADE INOPERABLE            
  |
|                                                                              |
| "On 02/18/02, at 1815 hours, the licensee discovered that the Beaver Valley  |
| Unit 2 #1 Emergency Diesel Generator had been rendered inoperable            |
| inadvertently, by the posting of a clearance at 1408 hours on 2/14/02. The   |
| #2 Emergency Diesel Generator had previously been removed from service for   |
| maintenance activities. Upon discovery that the #1 Emergency Diesel          |
| Generator was inoperable, action was immediately initiated to restore the #1 |
| Emergency Diesel Generator to Operable status. These actions were completed  |
| and the #1 Emergency Diesel Generator was restored to Operable status at     |
| 1830 hrs on 02/18/02.                                                        |
|                                                                              |
| "The #1 Diesel Generator was rendered inoperable at 1406 hrs on 02/14/02.    |
| During the period of inoperability, the licensee conducted core alterations  |
| including core reload during the ongoing ninth refueling outage. During the  |
| affected period, there were no challenges to the offsite power sources, and  |
| core cooling was maintained. Investigation into this event is ongoing.       |
|                                                                              |
| "This event is being reported under 10CFR50.72(v)(A) and 10CFR50.72(v)(B) as |
| a loss of Safe Shutdown Capability, and RHR Capability, respectively. There  |
| were no radiological releases associated with this event,"                   |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| * * * RETRACTION 1314 4/12/2002 FROM TOM COTTER TAKEN BY BOB STRANSKY * * *  |
|                                                                              |
| "Subsequent review and analysis of the event identified that the Unit 2 #1   |
| Emergency Diesel Generator (EDG) retained its capability to fulfil its       |
| safety function. During the time that the potential transformer fuses were   |
| inadvertently removed from the Unit 2 #1 EDG, the EDG would still have       |
| started and accelerated to proper speed and output voltage if a station loss |
| of offsite power had occurred. However, the output breaker would not have    |
| automatically closed and the EDG would not have automatically supplied       |
| emergency AC power to the Unit 2 A train emergency bus. Control room         |
| indications, powered by station DC sources, would have confirmed that the    |
| EDG was running at rated speed. Following station procedures, operations     |
| personnel would have attempted to locally close the A train EDG output       |
| breaker. The EDG output breaker would have closed, the EDG sequencer would   |
| have then have been automatically energized, and the required emergency      |
| loads would have been automatically sequenced on to the A train emergency    |
| bus. It is conservatively estimated that this action would have been         |
| completed within approximately 20-30 minutes. Unit 2 Residual Heat Removal   |
| (RHR) pumps are not automatically loaded onto an emergency bus for any       |
| postulated station loss of offsite power and would have to be manually       |
| loaded onto an emergency bus after a EDG is started. The estimated time      |
| frame to close the EDG output breaker and to load the RHR pump onto the EDG  |
| in this condition for a postulated loss of offsite power showed no           |
| significant adverse Unit results. Therefore, the EDG retained its capability |
| to fulfill its safety function.                                              |
|                                                                              |
| "This event will be reported as a Licensee Event Report pursuant to          |
| 10CFR50.73(a)(2)(i)(B)."                                                     |
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+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38844       |
+------------------------------------------------------------------------------+
                         
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 04/10/2002|
|LICENSEE:  TECHNICAL WELDING LAB INC            |NOTIFICATION TIME: 16:29[EDT]|
|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        04/10/2002|
|  COUNTY:  HARRIS                    STATE:  TX |EVENT TIME:        04:00[CDT]|
|LICENSE#:  L-02187               AGREEMENT:  Y  |LAST UPDATE DATE:  04/10/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KRISS KENNEDY        R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TEXAS DEPT OF HEALTH BRC     |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OVEREXPOSURE TO GAMMA RADIATION                                              |
|                                                                              |
| The following is taken from a facsimile report:                              |
|                                                                              |
| "A radiographer was [radiographing] welds on a vessel shooting with a 35     |
| curie Co-60 source and entered the vessel to change the source location      |
| without cranking the source into the shielded position. The radiographer has |
| been taken for blood samples which will be repeated in 72 hours. Initial     |
| calculations indicate a possible whole body exposure of 70 rems. Further     |
| information forthcoming after investigation scheduled for May 14."           |
|                                                                              |
| The Texas Incident Number for this event is I-7882.                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38848       |
+------------------------------------------------------------------------------+
                         
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| REP ORG:  BRISTOL-MYERS SQUIBB                 |NOTIFICATION DATE: 04/12/2002|
|LICENSEE:  BRISTOL-MYERS SQUIBB RADIOPHARMACEUTI|NOTIFICATION TIME:
16:15[EDT]|
|    CITY:  RIO TIADRIS              REGION:  2  |EVENT DATE:        04/12/2002|
|  COUNTY:                            STATE:  PR |EVENT TIME:             [EDT]|
|LICENSE#:  52-25361-01MD         AGREEMENT:  N  |LAST UPDATE DATE:  04/12/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KEN BARR             R2      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  FRANCIS ROY                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAD1 20.2202(a)(1)       PERS OVEREXPOSURE/TEDE |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL OVEREXPOSURE OF EXTREMITIES                                        |
|                                                                              |
| While investigating high ring dosimeter readings for two radiopharmacists    |
| involved in dispensing doses of Tc-99m, the licensee discovered that these   |
| individuals may have exceeded their occupational dose limits to the          |
| extremities for 2001. Ring dosimeter readings of 30-40 rem were recorded for |
| the individuals. During followup investigations, a certified health          |
| physicist, using fingertip dosimetry, determined that the individuals were   |
| receiving fingertip doses 3 to 7 times higher than those recorded on the     |
| ring dosimeters. Therefore, the individuals may have exceeded the annual     |
| occupational dose limit of 50 rem to the extremities.                        |
|                                                                              |
| The licensee will be providing a report to NRC Region II next week.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38849       |
+------------------------------------------------------------------------------+
                         
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| REP ORG:  WYLE LABORATORIES                    |NOTIFICATION DATE: 04/12/2002|
|LICENSEE:  WYLE LABORATORIES                    |NOTIFICATION TIME: 17:05[EDT]|
|    CITY:  HUNTSVILLE               REGION:  2  |EVENT DATE:        04/12/2002|
|  COUNTY:                            STATE:  AL |EVENT TIME:             [CDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/12/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |VERN HODGE (FAX)     NRR     |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  EDWARD SMITH (FAX)           |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT                                                        |
|                                                                              |
| "Pursuant to the 10 CFR Part 21 requirements, this letter notifies the NRC   |
| of a Potential Part 21 condition.                                            |
|                                                                              |
| "An error in irradiation dose units is identified in the attached letter     |
| from Georgia Tech letter dated March 15, 2002, which was received by Wyle on |
| April 11, 2002. The error applies to all equipment irradiated with the       |
| cobalt-60 sources in the Georgia Tech hot cell from 7/24/1997 to 7/6/2001.   |
| Georgia Tech reported radiation doses in units of rads-air (absorbed dose in |
| air) instead of Roentgens. Since one Roentgen is equal to 0.877 rad, the     |
| actual dose is less than the reported value.                                 |
|                                                                              |
| "Wyle will perform an evaluation to determine                                |
| "1. Wyle projects that include irradiation with the cobalt-60 sources in the |
| Georgia Tech hot cell from 7/24/1997 to 7/6/2001.                            |
| "2. The actual dose absorbed by equipment in said projects.                  |
| "3. Whether the actual dose in said projects envelops the customer-specified |
| requirements.                                                                |
|                                                                              |
| "Wyle Laboratories has the capability and chooses to perform the evaluation  |
| to determine if a defect exists. It is the responsibility to Wyle            |
| Laboratories to inform the purchaser(s), and any affected licensees.         |
|                                                                              |
| "Wyle will complete the specified evaluation of the circumstances within     |
| sixty (60) days of discovery of the potential defect. The NRC will be        |
| provided a copy of Wyle's evaluation report."                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38850       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 04/12/2002|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 17:37[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/12/2002|
+------------------------------------------------+EVENT TIME:        08:38[EDT]|
| NRC NOTIFIED BY:  KENNY MIDDLEBROOKS           |LAST UPDATE DATE:  04/12/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KEN BARR             R2      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY REPORT                                                      |
|                                                                              |
| A contract supervisor tested positive for alcohol use during a for-cause     |
| test. The individual's site access has been terminated. Contact the NRC      |
| Operations Center for additional information.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38851       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 04/12/2002|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 18:26[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        04/12/2002|
+------------------------------------------------+EVENT TIME:        16:36[CDT]|
| NRC NOTIFIED BY:  JAMES CRABILL                |LAST UPDATE DATE:  04/12/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KRISS KENNEDY        R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| Safeguards system degradation related to detection. Immediate compensatory   |
| measures taken upon discovery. Contact the NRC Operations Center for         |
| additional details. The NRC resident inspector will be informed of this      |
| event by the licensee.                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38852       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 04/13/2002|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 14:51[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        04/13/2002|
+------------------------------------------------+EVENT TIME:        13:17[EDT]|
| NRC NOTIFIED BY:  MATUSZEWSKI                  |LAST UPDATE DATE:  04/13/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KEN BARR             R2      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|4     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF ERDADS/ERDS                                                          |
|                                                                              |
| The licensee reported that the Emergency Response Data Acquisition and       |
| Display System (ERDADS) and Emergency Response Data System (ERDS) became     |
| inoperable due to the loss of both trains of the Data Link System. The       |
| licensee is currently attempting to restore the DLS. The NRC resident        |
| inspector will be informed of this notification by the licensee.             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38853       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 04/14/2002|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 16:25[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/14/2002|
+------------------------------------------------+EVENT TIME:        12:00[EDT]|
| NRC NOTIFIED BY:  A. DEES                      |LAST UPDATE DATE:  04/14/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KEN BARR             R2      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(3)(xii)    OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIALLY CONTAMINATED PERSON TRANSPORTED OFFSITE BY AMBULANCE.       
    |
|                                                                              |
| This report is being made to communicate the transportation of a potentially |
| radioactive contaminated person to an offsite medical facility for treatment |
| under 10CFR 50.72 (b)(3)(xii).  At 1138 EDT the Unit 1 Control Room was      |
| notified that an individual had fallen on the Refueling Floor striking her   |
| head on the floor.  The First Responders and Health Physics personnel        |
| responded to attend the individual and requested that the injured person be  |
| transported offsite to the Appling General Hospital in Baxley, Ga.  At 1200  |
| EDT the individual was transported offsite via ambulance.  The individual    |
| left offsite prior to the initial onsite survey for radioactive              |
| contamination had been completed.  This report is being made since there was |
| a potential for contamination.  The initial survey was completed at the      |
| hospital and it was determined that neither the individual nor any clothing  |
| was contaminated.                                                            |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38854       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 04/15/2002|
|    UNIT:  [] [2] []                 STATE:  TN |NOTIFICATION TIME: 02:59[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/15/2002|
+------------------------------------------------+EVENT TIME:        00:16[EDT]|
| NRC NOTIFIED BY:  SIMMONS                      |LAST UPDATE DATE:  04/15/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KEN BARR             R2      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT HAD ESF ACTUATION RESULTING IN AUTOMATIC REPOSITIONING OF AUX         
|
| FEEDWATER VALVES.                                                            |
|                                                                              |
|                                                                              |
| Unit 2 was in mode 3 and stable following the completion of a preplanned     |
| shutdown for a refueling outage.  The aux feedwater was in service at the    |
| time of this actuation.  The AFW Level Control Valves had been throttled,    |
| the "B" Main Feedwater Pump reset and Feedwater Isolation (FWI) reset to     |
| accordance with procedures.  The RCS Tavg drifted above 550F.   When the    |
| RCS Tavg dropped below 550F, a FWI signal was generated causing the reset   |
| Main Feedwater Pump to trip and the Aux Feedwater valves to reposition open. |
| The Aux Feedwater pumps were already running.   An investigation is          |
| ongoing.                                                                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+