Event Notification Report for December 31, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/30/2002 - 12/31/2002
** EVENT NUMBERS **
39406 39474 39478 39480
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39406 |
+------------------------------------------------------------------------------+
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| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 11/26/2002|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 08:24[EST]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 11/26/2002|
+------------------------------------------------+EVENT TIME: 03:42[CST]|
| NRC NOTIFIED BY: BRUCE FRANZEN |LAST UPDATE DATE: 12/30/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES CREED 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 97 Power Operation |97 Power Operation |
| | |
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EVENT TEXT
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| UNIT 2 HPCI SYSTEM DECLARED INOPERABLE |
| |
| Unit 2 HPCI (High Pressure Coolant Injection) system was declared inoperable |
| at 0342 [CST] due to a failed relay for the MGU (Motor Gear Unit) flow |
| control circuit. The relay is normally energized when the MGU is at the |
| High Speed Stop and is utilized to de-energize the motor gear unit when a |
| limit switch is reached to prevent damage to the MGU motor. The resultant |
| failure affects HPCI such that the MGU will not function from a signal |
| generated by the Flow Indicating Controller. HPCI can be operated manually |
| from [the] Control Room. |
| |
| The Resident Inspector was notified of this event. |
| |
| *** EVENT RETRACTION FROM ROBERT BROCH TO ARLON COSTA ON 12/30/02 AT 1326 |
| *** |
| |
| "On November 26, 2002 at 0724 CST, Dresden Station made an ENS Notification |
| (EN 39406) regarding a High Pressure Coolant Injection inoperability due to |
| a failed relay for the Motor Gear Unit (MGU) flow control circuit. It was |
| reported that the failed relay affected HPCI such that the MGU would not |
| function from a signal generated by the Flow Indicating Controller. The MGU |
| was capable of being operated from the Control Switch in the Control Room at |
| all times. The condition was reported, in accordance with 10 CFR |
| 50.72(b)(3)(v)(D), as reduction in accident mitigation capability. |
| |
| "Upon further evaluation of the issue, the following conclusions were |
| reached: In the event that HPCI would have automatically initiated following |
| the failure of the relay, the Motor Speed Changer (MSC) would have run to |
| the High Speed Stop (HSS). When the turbine reached 4000 rpm and flow |
| increased the MGU would have remained at the HSS. Therefore, HPCI would have |
| continued to operate at 4000 rpm and maximum injection flow (>5000 gpm) |
| until the system restored reactor water level to +48" (at which point the |
| turbine trips) or the Control Room Operator took manual control. It is |
| important to note at this point that even if the flow controller circuitry |
| is operational, the system would have responded in the same manner described |
| above. If no operator action was assumed following the relay failure, HPCI |
| would have increased reactor water level to the high water trip for break |
| sizes within its capability. |
| |
| "NUREG 1022 states that the intent of the 10 CFR 50.72 and 50 .73 reporting |
| criteria is to capture events where there would have been a failure of a |
| safety system to properly complete a safety function. In the above described |
| condition, the HPCI system was still capable to perform its intended safety |
| function. The system would have automatically started on an initiation |
| signal, come up to speed (4000 rpm), and provided >5000 gpm to the reactor |
| vessel. Additionally, the restart capability of the system was not affected |
| by the relay failure. Therefore, the system would have operated long enough |
| to complete its intended safety function as defined in the safety analysis |
| report. |
| |
| "Based on the above evaluation, HPCI was capable of performing its functions |
| as specified in the Technical Specifications, the safety analysis report and |
| met all of the operability requirements specified by the plant licensing |
| basis. |
| Based on these conclusions, EN #39406 is being retracted. |
| |
| The NRC Resident Inspector and the R3DO(Lanksbury) were notified. |
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|General Information or Other |Event Number: 39474 |
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| REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 12/26/2002|
|LICENSEE: SCHLUMBERGER TECHNOLOGIES CORP. |NOTIFICATION TIME: 11:35[EST]|
| CITY: RIFLE REGION: 4 |EVENT DATE: 12/26/2002|
| COUNTY: STATE: CO |EVENT TIME: 08:30[MST]|
|LICENSE#: 039-01 AGREEMENT: Y |LAST UPDATE DATE: 12/26/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| |SUSAN FRANT (email) NMSS |
+------------------------------------------------+FRED BROWN (email) NMSS |
| NRC NOTIFIED BY: TIM G. BONZER | |
| HQ OPS OFFICER: ARLON COSTA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE NOTIFICATION OF IRRETRIEVABLE WELL-LOGGING SOURCE |
| |
| Timothy Bonzer of the Colorado Radiation Services notified the NRC |
| Operations Center via fax on 12/26/02 at 1135 EST on an incident involving |
| an abandoned well-logging source assembly at a gas well near Rifle, Colorado |
| by Schlumberger Technologies Corp. The sources (Cs and AmBe) were lost at |
| approximately the 8,000 ft level and efforts to retrieve the sources were |
| unsuccessful. They had taken the necessary measures to deflect any future |
| attempt to drill in the same location and will place a stainless steel |
| warning placard at the surface. They intended to abandon the sources and are |
| still planning to use the well for the production of natural gas. |
| |
| The Colorado Emergency Management organization is cognizant of this |
| incident. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39478 |
+------------------------------------------------------------------------------+
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| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 12/30/2002|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 15:51[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/30/2002|
+------------------------------------------------+EVENT TIME: 14:15[CST]|
| NRC NOTIFIED BY: DAVE BUTLER |LAST UPDATE DATE: 12/30/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JOHNSON R4 |
|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 Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE EMERGENCY SIRENS DUE TO LIGHTNING STRIKES |
| |
| All emergency sirens (66 of 66) serving Hood and Somervell Counties, TX are |
| out of service due to lightning strikes on communications repeater |
| equipment. The licensee has notified the Hood and Somervell County Sheriff |
| Departments and will be notifying the NRC resident inspector. Repair crews |
| are responding and expect to make repairs within about 4 hours. |
| |
| ***UPDATE on 12/31/02 at 0113ET by Don Cerny taken by MacKinnon**** |
| |
| All sirens were returned to service December 31, 2002 at midnight. NRC |
| R4DO (Bill Johnson) notified. |
| |
| The NRC Resident Inspector will be contacted by the licensee of this update. |
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|Power Reactor |Event Number: 39480 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 12/31/2002|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 01:34[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 12/30/2002|
+------------------------------------------------+EVENT TIME: 20:10[CST]|
| NRC NOTIFIED BY: JAMES McKAY |LAST UPDATE DATE: 12/31/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| MONTICELLO INITIATED TS REQUIRED PLANT SHUTDOWN DUE TO INOPERABILITY OF BOTH |
| EDGs |
| |
| "With #12 EDG inoperable due to a maintenance issue [on 12/29/02 at 2330 |
| CST] , it is required to test #11 EDG within 24 hours. Testing causes #11 |
| EDG to be inoperable, therefore both EDGs are inoperable requiring [the |
| initiation of] a plant shutdown per T.S. 3.9.B.3.a.2 and a non-emergency |
| notification per 10 CFR 50.72/8 hour. #11 EDG subequently tested operable |
| and the plant exited T.S. shutdown requirement at 2300 on 12/30/02." |
| |
| The licensee stated that the period of time both EDGs were inoperable was |
| from 2010 to 2300 on 12/30/02. The inoperablity of the #12 EDG was due to |
| an equipment problem with the DC fuel oil pump. After fixing the DC fuel |
| oil pump on the #12 EDG, the EDG was restarted and the "failure-to-start" |
| alarm lit and the "cranking" alarm lit and stayed in for 5 minutes. The |
| licensee is currently evaluating these problems. The #12 EDG remains in a 7 |
| day limiting LCO action statement. The #11 EDG started and tested |
| satisfactorily with no problems. The inoperability of the #11 EDG was due to |
| some of the set up conditions for testing when the EDG is considered to be |
| inoperable per procedure. |
| |
| The NRC Resident Inspector was notified. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021