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Event Notification Report for February 26, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/23/2001 - 02/26/2001

                              ** EVENT NUMBERS **

37773  37774  37775  37776  37777  37778  37779  37780  

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|Other Nuclear Material                           |Event Number:   37773       |
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| REP ORG:  U.S. ARMY                            |NOTIFICATION DATE: 02/23/2001|
|LICENSEE:  U.S. ARMY                            |NOTIFICATION TIME: 13:16[EST]|
|    CITY:                           REGION:     |EVENT DATE:        12/15/2000|
|  COUNTY:                            STATE:     |EVENT TIME:        12:00[EST]|
|LICENSE#:  19-30653-01           AGREEMENT:  N  |LAST UPDATE DATE:  02/23/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GLENN MEYER          R1      |
|                                                |MARK RING            R3      |
+------------------------------------------------+BRIAN SMITH          NMSS    |
| NRC NOTIFIED BY:  JOYCE KUYKENDALL             |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| THREE CHEMICAL AGENT MONITORS FOUND MISSING DURING AN INVENTORY CHECK.       |
|                                                                              |
| During an inventory check on 12/15/2000 by the First Signal Brigade Unit     |
| located in Yongsan, Korea,  it was discovered that 3 chemical agent monitors |
| each containing 15mCi's of Nickel-63 were found missing.  An investigation   |
| into the loss of the three chemical agent monitors was initiated.            |
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|Power Reactor                                    |Event Number:   37774       |
+------------------------------------------------------------------------------+
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| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 02/23/2001|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 14:50[EST]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        02/20/2001|
+------------------------------------------------+EVENT TIME:        21:09[PST]|
| NRC NOTIFIED BY:  CLAY WILLIAMS                |LAST UPDATE DATE:  02/23/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|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        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 SHIFT SUPERVISOR TESTED POSITIVE FOR ALCOHOL DURING A RANDOM FITNESS  |
| FOR DUTY TEST.                                                               |
|                                                                              |
| "On February 20, 2001, after reporting for a non-scheduled work shift at     |
| about 1800 PST, the supervisor was informed he had been selected for a       |
| random fitness for duty (FFD) test. As allowed by plant procedures, the      |
| supervisor entered the protected area (PA) at about 1820 PST, but not any    |
| vital areas, before reporting for FFD testing at about 2000 PST.  At 2019,   |
| breathalyzer test results were positive for alcohol.  The supervisor         |
| requested that a blood sample be used for confirmatory testing.  Pending     |
| blood sample testing results, the supervisor's PA access was immediately     |
| terminated and he was placed on investigatory suspension.                    |
|                                                                              |
| "On February 23, 2001, during an NRC inspection exit interview, NRC          |
| inspectors commented that SCE should not wait on blood testing results to    |
| determine reportability of this occurrence.  Consequently, even though       |
| evaluation of the blood sample test results by the Medical Review Officer    |
| (MRO) have not been completed, SCE is reporting this occurrence .  SCE will  |
| implement appropriate disciplinary actions if completion of the blood sample |
| test result evaluation by the MRO confirms the initial test results."        |
|                                                                              |
| The NRC Resident Inspector will be notified of this event report.            |
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|General Information or Other                     |Event Number:   37775       |
+------------------------------------------------------------------------------+
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| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 02/23/2001|
|LICENSEE:  WAHLUKE PRODUCE, INC.                |NOTIFICATION TIME: 18:14[EST]|
|    CITY:  MATTAWA                  REGION:  4  |EVENT DATE:        02/18/2001|
|  COUNTY:                            STATE:  WA |EVENT TIME:        00:00[PST]|
|LICENSE#:  WN-I0332-1            AGREEMENT:  Y  |LAST UPDATE DATE:  02/23/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY FRAZEE                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| A TROXLER MODEL 4302 GAUGE AND A CPN MODEL 503 GAUGE WERE REDUCED TO CHARRED |
| METAL IN A FIRE. NO EARLY INDICATION OF RADIOACTIVE LEAKAGE.                 |
|                                                                              |
| In the early morning of Sunday, February 18, a fire destroyed the Wahluke    |
| Produce, Inc.,  office and potato processing building.  The building was     |
| also used for storage of two portable gauges containing radioactive          |
| material.  A Troxler Model 4302 depth probe, serial number 116, containing   |
| 11 millicuries (407 megabecquerels) of americium 241/beryllium and a CPN     |
| Model 503 soil probe, serial number H36066789, containing 50 millicuries     |
| (1850 megabecquerels) of americium 241/beryllium, were reduced to charred    |
| metal and ash.  The sealed sources were stored in their shields and          |
| transport boxes at the time of the fire.  All records of the business were   |
| destroyed in the fire, including the radioactive materials license and       |
| related information such as how to contact the department.  The licensee was |
| able to reach the gauge consultant who in turn notified the department on    |
| February 22, 2001.  Department staff responded to the scene on February 23   |
| and dug the two gauges out of approximately two feet of ash and debris.  The |
| gauges were surveyed and placed in 5 gallon buckets in a secure area to      |
| await retrieval by the licensee's gauge consultant that evening.  There was  |
| no early indication of leakage based on the department's survey and a leak   |
| test and shielding evaluation will be done by the consultant.  The fire      |
| remains under investigation although at this time it is not believed to have |
| been arson.                                                                  |
|                                                                              |
| What was the notification or reporting criteria involved?  WAC 246-221-250   |
|                                                                              |
| Washington State Report number WA-01-006                                     |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37776       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 02/23/2001|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 20:11[EST]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        02/23/2001|
+------------------------------------------------+EVENT TIME:        16:05[EST]|
| NRC NOTIFIED BY:  JEFF DEAL                    |LAST UPDATE DATE:  02/23/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRIAN BONSER         R2      |
|10 CFR SECTION:                                 |                             |
|*COM 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                                   
+------------------------------------------------------------------------------+
| EMERGENCY RESPONSE DATA ACQUISITION AND DISPLAY SYSTEM  (ERDADS) FAILED.     |
|                                                                              |
| At 1605 ET ERDADS CPU module overheated and failed, causing a loss of the    |
| ERDADS system.  ERDADS system was returned to service at 1710 ET.            |
|                                                                              |
| The NRC Resident Inspector will be notified by the licensee of this event.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37777       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 02/24/2001|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 00:53[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/23/2001|
+------------------------------------------------+EVENT TIME:        22:20[EST]|
| NRC NOTIFIED BY:  BILL WOODBURY                |LAST UPDATE DATE:  02/24/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRIAN BONSER         R2      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|*ESF 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     M/R        Y       37       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM DURING PLANT SHUTDOWN                                   |
|                                                                              |
| "On 02/23/01, at 22:20 during a planned Brunswick Unit 2 reactor shutdown    |
| for refueling a manual reactor scram was inserted.  The sequence of events   |
| was as follows.   At approximately 37% reactor power a turbine EHC           |
| malfunction annunciator was received and turbine bypass valves were observed |
| opening.   A turbine trip occurred on generator reverse power.   A generator |
| primary lockout signal caused the site's four emergency diesels to start.    |
| The emergency busses remained powered from offsite power, therefore the      |
| diesels did not load.   With the turbine control system malfunction, a       |
| manual reactor scram was inserted.   An expected reactor vessel level shrink |
| occurred where level lowered to approximately 150"  (normal vessel level is  |
| approximately 187").   This vessel level caused a group 2 and group 6        |
| isolation signal for the respective primary containment isolation valves.    |
| These valves isolated properly."                                             |
|                                                                              |
| An investigation is in progress to understand the cause of the turbine       |
| control system malfunction.   Other plant systems functioned as designed.    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37778       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 02/24/2001|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 01:13[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/23/2001|
+------------------------------------------------+EVENT TIME:        21:19[EST]|
| NRC NOTIFIED BY:  PETE ORPHANOS                |LAST UPDATE DATE:  02/24/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          R1      |
|10 CFR SECTION:                                 |                             |
|*SHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|*ESF 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     M/R        Y       45       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP - SAFETY/RELIEF VALVE OPENED AT POWER                    |
|                                                                              |
| Unit 2 was manually shutdown as required by plant procedures and Technical   |
| Specifications for an actuation of a single reactor coolant system           |
| safety/relief valve.  A rapid plant shutdown from critical at 85% power was  |
| performed.  The shutdown required a manual actuation of the reactor          |
| protection system.   All rods inserted normally on the manual scram.   All   |
| plant systems operated as expected.   Reactor level decreased below the low  |
| level 3 reactor protection setpoint immediately following the scram as a     |
| result of normal system response.                                            |
|                                                                              |
| Current plant conditions: The reactor is in HOT SHUTDOWN at 106 psig         |
| progressing towards COLD SHUTDOWN.  Reactor level is stable being controlled |
| by condensate injection. The safety/relief valve remains open.   Suppression |
| Pool Cooling is in service with pool temperature 94 degrees Fahrenheit.      |
|                                                                              |
| The 2N SRV was the one that opened.  The licensee had been in the process of |
| shutting down to make repairs to this valve when it fully opened.  It is     |
| believed to have a faulty pilot valve.                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 0859 ON 2/24/01 BY RICH RECEIVED BY WEAVER * * *             |
|                                                                              |
| The 2N reactor coolant safety/relief valve reseated at 130 psig reactor      |
| coolant pressure.  The MSIVs were reopened and plant cool down continued.    |
| Unit 2 is currently in OPCON 4 with the "2B" Loop of Shutdown Cooling in     |
| service.   Reactor coolant temperature is less than 200 degrees F.    The    |
| licensee notified the NRC resident inspector.   R1DO (Meyer) notified.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37779       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 02/24/2001|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 03:24[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        02/24/2001|
+------------------------------------------------+EVENT TIME:        03:06[EST]|
| NRC NOTIFIED BY:  RAY MARTIN                   |LAST UPDATE DATE:  02/24/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          R1      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Refueling        |0        Refueling        |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFEGUARDS DEGRADATION RELATED TO AREA BOUNDARY                              |
|                                                                              |
| IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY                          |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.   ADDITIONAL DETAILS MAY   |
| BE OBTAINED FROM THE OPERATIONS CENTER.                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37780       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 02/24/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 18:04[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        02/24/2001|
+------------------------------------------------+EVENT TIME:        15:10[CST]|
| NRC NOTIFIED BY:  J. TEMPLE                    |LAST UPDATE DATE:  02/24/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK RING            R3      |
|10 CFR SECTION:                                 |ELINOR ADENSAM       NRR     |
|*SHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |FRANK CONGEL         IRO     |
|*IND 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          Y       100      Power Operation  |94       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) AND BOTH INJECTION PATHS OF LOW       |
| PRESSURE COOLANT INJECTION (LPCI) DECLARED INOPERABLE.                       |
|                                                                              |
|                                                                              |
| HPCI and both injection paths of LPCI have been declared inoperable as a     |
| result of not meeting inservice testing of injection check valves as         |
| required by Technical Specification 4.15.B.  Technical Specification         |
| shutdown required by Technical Specification 3.5.A (4), be in a Hot Shutdown |
| condition within 24 hours (start time 1510 CT) . Plant shutdown commenced at |
| 1608 CT.                                                                     |
|                                                                              |
| Licensee was reviewing ASME Code Section XI requirements as a result of a    |
| snubber problem encountered last week.  While reviewing ASME Code Section XI |
| requirements it was determined that HPCI and LPCI injection test valves may  |
| not meet ASME Code Section XI inservice testing requirements as specified    |
| per their Technical Specification.  The reactor has to be shutdown in order  |
| to test the LPCI injection test valves since personnel have to enter the     |
| drywell.   A soft shutdown of the reactor will be performed (the reactor     |
| will not be scrammed from power).  All other Emergency Core Cooling Systems  |
| and the Emergency Diesel Generators are fully operable if needed. Electrical |
| grid is stable.                                                              |
|                                                                              |
| The NRC Resident Inspector will be notified by the licensee of this event.   |
+------------------------------------------------------------------------------+