Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for April 12, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/11/2006 - 04/12/2006

** EVENT NUMBERS **

42489

42490

42491

Power Reactor	Event Number: 42489
Facility: SUSQUEHANNA Region: 1 State: PA Unit: [1] [ ] [ ] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: GRANT FERNSIER HQ OPS Officer: BILL GOTT	Notification Date: 04/11/2006 Notification Time: 09:35 [ET] Event Date: 03/11/2006 Event Time: 04:32 [EST] Last Update Date: 04/11/2006
Emergency Class: NON EMERGENCY 10 CFR Section: 50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION	Person (Organization): JAMES NOGGLE (R1)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	N	N	0	Refueling	0	Refueling

Event Text

INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES

"On 03/11/06 at approximately 0432 hours, with Susquehanna Unit 1 in the Refueling Mode (0% power), the Unit experienced a partial isolation of Primary Containment isolation valves. The actuation occurred when a blown fuse disrupted power to a containment isolation logic relay. The inboard isolation valve to the 'B' Drywell Floor Drain Sump and the Containment Instrument Gas purge supply valve to the TIP indexer both closed. The 'A' Standby Gas Treatment system fan and the 'A' Reactor Building Recirculation fan successfully auto started during the event.

"This event constitutes an invalid system actuation and is reportable under 10CFR 50.73(a)(2)(iv)(A). The condition meets the criteria of 10CFR 50.73(a)(2)(iv)(B)(2) because a general containment isolation signal affected containment isolation valves in more than one system. This notification is being provided via a 60-day optional phone call as permitted under 10CFR 50.73(a)(1) in lieu of a written LER.

"As stated above, both valves affected by the invalid signal fulfilled their isolation function by successfully closing. At the time of the event, no other Primary Containment isolation valve was being maintained in a manner that required re-positioning. There were no challenges to the Reactor as a result of this event. The plant responded as expected.

"Following replacement of the subject fuse, the isolation logic was successfully reset and affected equipment was restored to the desired status."

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 42490
Facility: HATCH Region: 2 State: GA Unit: [1] [2] [ ] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: ALAN WOLFE HQ OPS Officer: BILL GOTT	Notification Date: 04/11/2006 Notification Time: 11:06 [ET] Event Date: 04/10/2006 Event Time: 16:25 [EDT] Last Update Date: 04/11/2006
Emergency Class: NON EMERGENCY 10 CFR Section: 26.73 - FITNESS FOR DUTY	Person (Organization): BRIAN BONSER (R2)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	N	Y	100	Power Operation	100	Power Operation
2	N	Y	100	Power Operation	100	Power Operation

Event Text

FITNESS FOR DUTY

A contract employee supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 42491
Facility: BEAVER VALLEY Region: 1 State: PA Unit: [ ] [2] [ ] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: ANDREW HEWITT HQ OPS Officer: JOE O'HARA	Notification Date: 04/11/2006 Notification Time: 12:37 [ET] Event Date: 04/11/2006 Event Time: 09:24 [EDT] Last Update Date: 04/11/2006
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(i) - PLANT S/D REQD BY TS	Person (Organization): JAMES NOGGLE (R1)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
2	N	Y	100	Power Operation	65	Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN

"At 0924 Unit 2 experienced multiple Fire Protection System Deluge Valve actuations for the Main Filter Banks, System Station Service Transformers (SSSTs) 2A and 2B, the Main Transformer, Condensate Polishing building ventilation charcoal filter and Decontamination building ventilation charcoal filter. The Transformers were unaffected by the spray actuation and remained operable.

"No actual fire occurred or was observed for these components or areas. The Motor driven and Engine Driven Fire Pumps automatically started upon the actuations. These above noted areas and components received water spray down until manually isolated.

"It was verified that both of the Charcoal Main Filter Banks (TS 3.7.8.1) had become wetted down by the spray actuation. With the charcoal main filter banks wet, their filtering capability becomes impacted and is being evaluated. These filter components were declared inoperable.

"At 0924, Unit 2 entered the actions of Tech. Spec. 3.0.3. The requirements of Tech Spec 3.0.3 are:

"Within 1 hour action shall be initiated to place the unit in Hot Standby within the following 6 hours, Hot Shutdown within the following 6 hours, and Cold Shutdown within the subsequent 24 hours. At 1055 Unit 2 commenced shutdown at 20%/hr.

"The cause of the multiple actuations is not understood at this time. An Event Response Team has been formed to investigate the issue."

All other safety related systems are operable. The action required for the licensee to exit this Tech Spec required shutdown will be to restore the charcoal filter banks to operable status. The licensee estimates the investigation, troubleshooting, and repair efforts to last approximately 40 hours.

The licensee notified the NRC Resident Inspector.

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