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
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39439 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39440 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39441 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| "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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021