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Event Notification Report for April 23, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/22/2009 - 04/23/2009

** EVENT NUMBERS **


45008 45009 45010

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Power Reactor Event Number: 45008
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: GENE DORMAN
HQ OPS Officer: KARL DIEDERICH
Notification Date: 04/22/2009
Notification Time: 13:03 [ET]
Event Date: 04/22/2009
Event Time: 11:21 [EDT]
Last Update Date: 04/22/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PAUL KROHN (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM INOPERABLE

"On 4/22/09 at approximately 1121, during surveillance testing on the High Pressure Coolant Injection (HPCI) System, the associated Primary Containment Isolation valves closed. This isolation rendered the HPCI system incapable of performing its safety function and is, therefore, reportable under 10 CFR 50.72(b)(3)(v). Technical Specification LCO 3.5.1 Condition C had been entered at 0837 to support testing. The cause of the isolation is unknown at this time. Troubleshooting is in progress. LCO 3.5.1 Condition C provides 14 days for restoration of the HPCI System, the plant will remain in the LCO until the cause is determined and any associated repairs have been completed.

"A follow-up Licensee Event Report will be filed within 60 days.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 45009
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DENNIS MAY
HQ OPS Officer: KARL DIEDERICH
Notification Date: 04/22/2009
Notification Time: 13:37 [ET]
Event Date: 03/24/2009
Event Time: 13:26 [EDT]
Last Update Date: 04/22/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
PAUL KROHN (R1DO)

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

Event Text

PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) GROUP 3 INVALID ACTUATION

"This sixty day notification is being made in accordance with 10 CFR 50.73(a)(2)(iv)(A) to provide the NRC with information pertaining to an unplanned invalid actuation of specific systems, specifically, a Primary Containment Isolation System (PCIS) Group 3 actuation signal that affected containment isolation valves in more than one system.

"On March 24, 2009, at approximately 1326 hours, Vermont Yankee Nuclear Power Station (VYNPS) experienced an invalid PCIS Group 3 isolation associated with personnel error during quarterly calibration of the Refuel Floor Zone Radiation Monitors. VYNPS had removed the East Refuel Floor Zone Radiation Monitor from service for calibration. The technician, in the field, had completed a phone communication with the control room and was dispatched to the East Refuel Floor Zone Radiation Monitor to perform the calibration activity. However, the technician incorrectly went to the inservice West Refuel Floor Zone Radiation Monitor and removed the detector from service. This incorrect action caused a momentary invalid high radiation signal containment isolation signal and the Subsequent PCIS Group 3 isolation. The following actuations resulted:

"Both trains of the Standby Gas Treatment System started as designed.

"The PCIS functioned properly providing a complete Group 3 isolation valves in the following system actuated as a result of the PCIS Group 3 isolation:

"Drywell Air Purge and Vent,
"Drywell and Suppression Chamber Main Exhaust,
"Suppression Chamber Purge and Vent,
"Containment Air Compressor Suction,
"Exhaust to Standby Gas Treatment,
"Containment Purge Supply and Makeup,
"Containment Air Sampling,
"Air Dilution Subsystem, [and]
"Containment Air Dilution Vent System.

"This event has been entered into VYNPS's corrective action program."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 45010
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JEFFREY A. MIELL
HQ OPS Officer: VINCE KLCO
Notification Date: 04/23/2009
Notification Time: 02:33 [ET]
Event Date: 04/22/2009
Event Time: 19:45 [CDT]
Last Update Date: 04/23/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMNES CAMERON (R3DO)

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

Event Text

HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE

"On 4/22/2009 during an inspection of the HPCI (High Pressure Coolant Injection) Suppression Pool Suction piping it was identified that the suction piping was in contact with a piping support clamp. Per the design of the support, the clamp ring to pipe clearance should be 1/2 inch. With the identified contact, the integrity of the pipe support cannot be assured during a seismic event. At the time of discovery, the HPCI suction was aligned to the Suppression Pool. Subsequently, the suction has been realigned to the Condensate Storage Tank with both Suppression Pool suction valves deenergized in the closed position. HPCI remains available with suction aligned to the Condensate Storage Tank.

"Due to this, HPCI was declared INOPERABLE on 4/22/2009 at 7:45 PM (local time). This event is reportable per 10 CFR 50.72(b)(3)(v)(D) for a single train safely system potentially unable to perform its safely function of accident mitigation.

The licensee entered a 14 day LCO (Limiting Condition of Operation) associated with the inoperable HPCI system.

"The NRC Resident Inspector has been notified."

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Thursday, March 29, 2012