Event Notification Report for December 20, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/19/2001 - 12/20/2001
** EVENT NUMBERS **
38581 38582 38583 38584 38585 38586
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|Power Reactor |Event Number: 38581 |
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| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 12/19/2001|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 04:47[EST]|
| RXTYPE: [1] CE |EVENT DATE: 12/19/2001|
+------------------------------------------------+EVENT TIME: 02:50[CST]|
| NRC NOTIFIED BY: CHRISTENSEN |LAST UPDATE DATE: 12/19/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GARY SANBORN R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| LOCAL FIRE DEPARTMENT NOTIFIED OF A FIRE ONSITE |
| |
| A fire alarm was received @ 0248 CST on 12/19/01 for room-22 safety |
| injection pump room. An inspection showed heavy smoke at entrance to |
| room. The plant fire brigade was manned and personnel entered the room. |
| The fire source was an extension cord, connected to some heaters, which |
| started some anti-contamination clothing on fire. The fire was identified @ |
| 0306 CST and declared out @ 0308 CST. The Blair Fire Department was |
| notified @ 0250 CST and responded to the site. No entry was made to the |
| Protected Area, as the fire was out upon their arrival. The licensee is |
| still investigating the cause. |
| |
| The NRC Resident Inspector was notified. |
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|General Information or Other |Event Number: 38582 |
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| REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 12/19/2001|
|LICENSEE: EXEMPLA ST. JOSEPH HOSPITAL |NOTIFICATION TIME: 10:36[EST]|
| CITY: DENVER REGION: 4 |EVENT DATE: 12/13/2001|
| COUNTY: STATE: CO |EVENT TIME: [MST]|
|LICENSE#: 38-33A AGREEMENT: Y |LAST UPDATE DATE: 12/19/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EGIDI | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| THE COLORADO DEPARTMENT OF PUBLIC HEALTH AND ENVIRONMENT REPORTED A
POSSIBLE |
| MEDICAL MISADMINISTRATION BY ONE OF THEIR LICENSEES |
| |
| This occurred during a therapeutic administration of strontium - 90 when the |
| catheter being used shifted about 15 mm and ended up in the aorta instead of |
| a blood vessel. When the catheter was initially placed and the sources were |
| driven out, on the initial 30 second check everything was ok, but on the |
| second 30 second check, the catheter looked like it had moved, so the source |
| was retracted and the catheter repositioned. The source was out for |
| approximately 1 minute 15 seconds. After the repositioning the full |
| treatment(23 gray) was given to the patient. The patient was notified |
| through the referring physician. |
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|General Information or Other |Event Number: 38583 |
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| REP ORG: CENTRAL SOYA COMPANY |NOTIFICATION DATE: 12/19/2001|
|LICENSEE: CENTRAL SOYA COMPANY |NOTIFICATION TIME: 12:15[EST]|
| CITY: INDIANAPOLIS REGION: 3 |EVENT DATE: 12/14/2001|
| COUNTY: STATE: IN |EVENT TIME: [CST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 12/19/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MONTE PHILLIPS R3 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM ANDORFER | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
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EVENT TEXT
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| NUMEROUS GENERAL LICENSE TRITIUM EXIT SIGNS FOUND MISSING |
| |
| During a review of tritium exit signs on hand, the licensee discovered that |
| 28 of the 33 were missing. The 33 tritium signs shown in possession include |
| 24 manufactured by Self Powered, Inc (Qty 8 - Model 700C with 4700 |
| millicuries activity/each received on 2/15/89 and Qty 16 - Model 710 with |
| 25,000 millicuries activity/each received on 5/15/88) and 9 manufactured by |
| NRD LLC (Model T4001 with 8400 millicuries activity/each received on |
| 5/15/93). The missing signs include 19 Self Powered units (specific models |
| not identified at time of report) and all 9 NRD units. The facility in |
| Indianapolis where these signs were installed experienced an explosion and |
| fire in 1993 and was subsequently demolitioned in 1996. The licensee |
| contacted NRC Region 3(Andrea Cook) and was advised to submit a written |
| report. |
| |
| * * * UPDATE 1459EST ON 12/19/01 FROM TOM ANDORFER TO S. SANDIN * * * |
| |
| The licensee updated their notification to identify that the 5 exit signs in |
| possession are the model 710. Notified R3DO(Phillips) and NMSS(Turner). |
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|Other Nuclear Material |Event Number: 38584 |
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| REP ORG: US ARMY |NOTIFICATION DATE: 12/19/2001|
|LICENSEE: US ARMY |NOTIFICATION TIME: 16:33[EST]|
| CITY: ABERDEEN REGION: 1 |EVENT DATE: 12/19/2001|
| COUNTY: STATE: MD |EVENT TIME: [EST]|
|LICENSE#: 19-30563-01 AGREEMENT: Y |LAST UPDATE DATE: 12/19/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN KINNEMAN R1 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOYCE KUYKENDALL | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| CHEMICAL AGENT MONITOR FAILED ANNUAL LEAK TEST |
| |
| A Chemical Agent Monitor containing a 15 millicurie Ni-63 source failed the |
| annual leak test. The swipe analyzed at the laboratory in Maryland measured |
| .006 microcuries which exceeds the .005 microcurie limit. The device was |
| manufactured by Environmental Technology Group, serial number 316-C-Q-2205, |
| and is currently in Pirmasens, Germany. Corrective action will be to double |
| bag and dispose of it as radwaste. |
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|Power Reactor |Event Number: 38585 |
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| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 12/19/2001|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 19:12[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 12/19/2001|
+------------------------------------------------+EVENT TIME: 16:00[CST]|
| NRC NOTIFIED BY: BRUCE SCHOENBACH |LAST UPDATE DATE: 12/19/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GARY SANBORN R4 |
|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 | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| EVENT OR CONDITION THAT COULD HAVE PREVENTED FULFILLMENT OF A SAFETY
|
| FUNCTION |
| |
| "The Callaway Plant Final Safety Analysis-Site Addenda, Chapter 2.4 |
| specifies controls to ensure site drainage paths are maintained to prevent |
| flooding of the safety related facilities during postulated design basis |
| precipitation events. Controls are specifically established to ensure |
| modifications to site grading and roadway elevations are evaluated to ensure |
| the Probable Maximum Precipitation (PMP) design basis is not adversely |
| affected and the safety-related structures are protected from flooding. |
| |
| "During installation of highway barriers at the site perimeter on December |
| 19, 2001, it was determined that the barrier installation had not been |
| properly evaluated to ensure the PMP design basis was not adversely |
| impacted. |
| |
| "It was concluded this event was reportable per 10 CFR 50.72(b)(3)(v) |
| because the barrier configuration, in conjunction with PMP conditions could |
| have prevented the fulfillment of the safety function of structures or |
| systems due to flooding. |
| |
| "Immediate actions have been initiated to remove the barriers, thus |
| restoring site grading and road elevations. These actions are targeted for |
| completion within the next twelve-hour shift. In addition, current weather |
| conditions are clear, with no precipitation forecast for the next 24 hours. |
| |
| "The NRC Resident Inspector was notified of this event by the licensee." |
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|Power Reactor |Event Number: 38586 |
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| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 12/20/2001|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 02:15[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/19/2001|
+------------------------------------------------+EVENT TIME: 23:19[EST]|
| NRC NOTIFIED BY: HUNT |LAST UPDATE DATE: 12/20/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|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/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| REACTOR AUTO TRIP FROM 100% POWER ON AMSAC SIGNAL |
| |
| While operating at 100% power, the Watts Bar Unit 1 reactor automatically |
| tripped at 2319 EST on December 19, 2001, due to an AMSAC signal which |
| resulted in a turbine/reactor trip. All control rods fully inserted |
| properly and the Auxiliary Feedwater (AFW) System started, as required, in |
| response to the AMSAC signal and the reactor trip. The steam generator |
| levels were at normal levels prior to the trip. No ECCS actuation occurred |
| and no relief valves lifted. The cause of the AMSAC signal is under |
| investigation. |
| |
| The NRC Resident Inspector was notified. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021