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Event Notification Report for December 13, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/12/2002 - 12/13/2002

                              ** EVENT NUMBERS **

39439  39440  39441  

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|Power Reactor                                    |Event Number:   39439       |
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| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 12/12/2002|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 00:20[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/11/2002|
+------------------------------------------------+EVENT TIME:        18:13[EST]|
| NRC NOTIFIED BY:  JIM CASE                     |LAST UPDATE DATE:  12/12/2002|
|  HQ OPS OFFICER:  JASON FLEMMING               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |
|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  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| RHR B MINIMUM CONTROL FLOW VALVE INOPERABLE                                  |
|                                                                              |
| "Scheduled maintenance activities were being performed on RHR B minimum flow |
| valve 1E12-F064B which is a containment isolation valve. When the E12-F064 B |
| power supply was energized the Control Room indication for the valve         |
| indicated intermediate.   Local indication for the valve indicated the valve |
| was closed.  When the valve control switch was taken to closed the valve was |
| observed to move 1/16 of an inch and the control room indication changed to  |
| full close. The valve was closed and verified down powered on 12/09/02 to    |
| comply with Tech Spec 3.6.1.3 Primary Containment Isolation Valves.          |
| Maintenance test equipment was installed however no maintenance had been     |
| performed."                                                                  |
|                                                                              |
| Licensee informed NRC resident inspector.                                    |
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|Power Reactor                                    |Event Number:   39440       |
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| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 12/12/2002|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 11:32[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        12/12/2002|
+------------------------------------------------+EVENT TIME:        08:20[EST]|
| NRC NOTIFIED BY:  JOHN SCHOLRK                 |LAST UPDATE DATE:  12/12/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID LEW            R1      |
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT ACTUATION OF OFFSITE EMERGENCY NOTIFICATION SIRENS               |
|                                                                              |
| "TMI is making a 4 hour report in accordance with 10 CFR 50.72 (b)(2)(xi) of |
| an event that occurred at approximately 8:20 AM on Thursday, December 12,    |
| 2002 when the offsite emergency sirens for TMI- 1 located in Dauphin County  |
| were  activated. The siren activation was not related to any condition or    |
| event at TMI- 1. The sirens sounded for only a few minutes (less than 10     |
| minutes). TMI- I has notified Dauphin County, the other risk counties and    |
| the Pennsylvania Emergency Management Agency of the inadvertent siren        |
| activation. The site NRC resident inspectors office has been informed of the |
| inadvertent activation and that a 4 hour notification is being made.         |
|                                                                              |
| "The cause of the inadvertent activation is not known at this time. This     |
| activation of the sirens has been entered into the site corrective action    |
| program to determine the cause and the actions necessary to prevent          |
| recurrence.                                                                  |
|                                                                              |
| "It is our understanding that Dauphin County has issued a press release      |
| regarding the activation of the sirens.                                      |
|                                                                              |
| "There was no impact on TMI-l due to the activation of the offsite sirens    |
| located in Dauphin County, Pennsylvania. The TMI- I alert and notification   |
| system remained operable for the duration of the event."                     |
|                                                                              |
| *** UPDATE ON 12/12/02 AT 1549 BY JOHN SCHORK TO ERIC THOMAS ***             |
|                                                                              |
| "On Thursday, December 12, 2002 at 11:32 am, TMI made a 4 hour report in     |
| accordance with 10 CFR 50.72 (b)(2)(xi) of an event that occurred at         |
| approximately 8:20 am on Thursday, December 12, 2002 when the offsite        |
| emergency sirens for  TMI-1 located in Dauphin County were inadvertently     |
| activated. This is an update to that notification.                           |
|                                                                              |
| "The TMI-1 sirens located in Dauphin County were inadvertently activated at  |
| 8:20 am on Thursday, 12/12/2002. The siren activation was not related to any |
| condition or event at TMI-1. The sirens sounded for only a few minutes (less |
| than 10 minutes). TMI-1 notified Dauphin County, the other risk counties and |
| the Pennsylvania Emergency Management Agency of the inadvertent siren        |
| activation.  The site NRC resident inspector's office was informed of the    |
| inadvertent activation and that a 4 hour notification was made.              |
|                                                                              |
| "During the afternoon of December 12, 2002, troubleshooting of the cause of  |
| inadvertent actuation that occurred at 8:20 am resulted in a second,         |
| momentary re-activation of the Dauphin County sirens at 1:43 pm. The         |
| troubleshooting was successful and the cause of the inadvertent actuation, a |
| software error in the access program for activation of the sirens, was       |
| identified. The risk counties and the Pennsylvania Emergency Management      |
| Agency have been notified of the second activation. In addition the site NRC |
| senior resident inspector has been notified of the second activation and our |
| intent to submit a revised 4 hour report.                                    |
|                                                                              |
| "The inadvertent activation of the sirens has been entered into the site     |
| corrective action program to determine the cause and the actions necessary   |
| to prevent recurrence.                                                       |
|                                                                              |
| "Dauphin County has issued a press release regarding the initial activation  |
| of the sirens.                                                               |
|                                                                              |
| "There was no impact on TMI-1 due to the initial activation of the offsite   |
| sirens at 8:20 am located in Dauphin County, Pennsylvania nor was there any  |
| impact on TMI-1 due to the second activation. The TMI-1 alert and            |
| notification system remained operable for the duration of both               |
| activations."                                                                |
|                                                                              |
| Notified R1DO David Lew.                                                     |
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|Power Reactor                                    |Event Number:   39441       |
+------------------------------------------------------------------------------+
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| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 12/12/2002|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 15:57[EST]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        10/20/2002|
+------------------------------------------------+EVENT TIME:        10:54[CDT]|
| NRC NOTIFIED BY:  ANTHONY BOLYEN               |LAST UPDATE DATE:  12/12/2002|
|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| "INVALID AFW SYSTEM ACTUATION                                                |
|                                                                              |
| "EVENT DESCRIPTION                                                           |
|                                                                              |
| "This report is being made in accordance with [10 CFR] 50.73(a)(1), which    |
| states, in part, 'In the case of an invalid actuation reported under [10     |
| CFR] 50.73(a)(2)(iv), other than actuation of the reactor protection system  |
| (RPS) when the reactor is critical, the licensee may, at its option, provide |
| a telephone notification to the NRC Operations Center within 60 days after   |
| discovery of the event instead of submitting a written LER.'  This invalid   |
| actuation is being reported under [10 CFR] 50.73(a)(2)(iv)(A).               |
|                                                                              |
| "NUREG-1022, Rev. 2, 'Event Reporting Guidelines 10CFR50.72 and 50.73        |
| provides guidance for determining if an actuation is invalid. The NUREG      |
| states, in part, that invalid actuations include actuations that are not the |
| result of valid signals and are not intentional manual actuations. Valid     |
| signals are those signals that are initiated in response to actual plant     |
| conditions or parameters satisfying the requirements for initiation of the   |
| safety function of the system. This report documents an actuation that was   |
| not the result of a valid signal and was not an intentional manual           |
| actuation. For these reasons, this event constitutes an invalid actuation.   |
|                                                                              |
| "NUREG-1022, Rev. 2, states that the report should provide the following     |
| information:                                                                 |
| - the specific train(s) and system(s) that were actuated,                    |
| - whether each train actuation was complete or partial, and                  |
| - whether or not the system started and functioned successfully.             |
|                                                                              |
| "On October 20, 2002 at 1054 CDST, the Turbine Driven Auxiliary Feedwater    |
| (TDAFW) pump auto-started as a result of an invalid signal. Investigation    |
| into the event has shown that the steam supply valve to the TDAFW pump       |
| (MS-102) opened inadvertently, starting the TDAFW Pump. Control room         |
| annunciators and computer points alarmed. Steam generator blowdown valves    |
| closed, per design, as a result of the TDAFW pump start. The TDAFW pump was  |
| placed to pullout after verifying that there were no valid automatic start   |
| signals."                                                                    |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
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