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Event Notification Report for February 26, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/25/2010 - 02/26/2010

** EVENT NUMBERS **


45718 45724 45726 45728

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Power Reactor Event Number: 45718
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: BRIAN VANGOR
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/23/2010
Notification Time: 16:00 [ET]
Event Date: 02/23/2010
Event Time: 01:00 [EST]
Last Update Date: 02/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE SCHMIDT (R1DO)

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

Event Text

ERDS NOT AVAILBLE DUE TO PLANT COMPUTER MALFUNCTION

"The Emergency Response Data System (ERDS) link from the Critical Function Monitoring System (CFMS) was lost at approximately 0100 hours on February 23, 2010 due to a malfunction of the plant computer. Other systems such as Safety Parameter Display System (SPDS), RECS, and ENS remain available. In accordance with the site reporting procedure, a loss of ERDS for greater than 16 hours is reportable as a major loss of emergency assessment capability. Troubleshooting is in progress."

The licensee has notified the NRC Resident Inspector and will notify the state.

* * * UPDATE FROM THOMAS RAS TO JOE O'HARA AT 1724 ON 2/25/10 * * *

ERDS was restored to operable status at 1652 EST.

The licensee notified the NRC Resident Inspector.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45724
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: JOHN MUSSER
HQ OPS Officer: PETE SNYDER
Notification Date: 02/24/2010
Notification Time: 18:10 [ET]
Event Date: 02/24/2010
Event Time: 11:40 [CST]
Last Update Date: 02/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
RYAN LANTZ (R4DO)

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

AUXILIARY FEEDWATER PUMPS MAY EXPERIENCE RUNOUT AT LOW STEAM PRESSURES

"At 1140 CST, both of the stations safety related auxiliary feedwater (AFW) pumps were declared inoperable. The AFW pumps were declared inoperable due to an evaluation that determined that the pumps may experience runout at low steam generator pressures during some design basis events. The stations Technical Specifications require that: 'With both AFW trains inoperable, then initiate actions to restore one AFW train to OPERABLE status immediately.' Technical Specification (TS) 2.0.1 and all TS actions requiring MODE change are suspended until one AFW train is restored to OPERABLE status.

"The station is aggressively working to develop a solution to return at least one train of the AFW system to operability."

The licensee notified the NRC Resident Inspector.


* * * UPDATE FROM DAVID SPARGO TO PETE SNYDER AT 2323 ON 2/24/10 * * *

"At 2133 CST, Steam Driven Auxiliary Feedwater Pump, FW-10, was declared operable based on an engineering evaluation that determined FW-10 will perform as required under all design basis conditions.

"Motor Driven Auxiliary Feedwater Pump, FW-6, remains inoperable. [The licensee] exited Technical Specification 2.0.1 and 2.5(1)D, and entered TS 2.5(1)B, 24 hour LCO, effective as of 1140 CST."

The licensee notified the NRC Resident Inspector. Notified R4DO (Lantz).


* * * UPDATE FROM DAVID SPARGO TO DONALD NORWOOD AT 0435 ON 2/25/10 * * *

At 0238 CST, Motor Driven Auxiliary Feedwater Pump, FW-6, was declared operable per an Engineering Operability Evaluation. [The licensee] exited Technical Specification 2.5(1)B.

The licensee notified the NRC Resident Inspector. Notified R4DO (Lantz).

* * * RETRACTION FROM ERICK MATZKE TO JOE O'HARA AT 1625 EST ON 2/25/10 * * *

"Further review has determined that the auxiliary feedwater pumps are and have been fully capable of performing their required safety function. Therefore, this notification is being retracted."

The licensee notified the NRC Resident Inspector. Notified R4DO(Lantz)

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Power Reactor Event Number: 45726
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID BORGER
HQ OPS Officer: JOHN KNOKE
Notification Date: 02/25/2010
Notification Time: 16:20 [ET]
Event Date: 02/25/2010
Event Time: 14:18 [EST]
Last Update Date: 02/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
WAYNE SCHMIDT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 94 Power Operation 94 Power Operation
2 N Y 94 Power Operation 94 Power Operation

Event Text

INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES

"This 60-day notification is being made in accordance with 10 CFR 50.73(a)(1), which states that in case of an invalid actuation reported under 10 CFR 50.73(a)(2)(iv)(A), other than the actuation of the Reactor Protection System (RPS) when the reactor is critical, the licensee may provide a telephone notification to the NRC within 60 days after discovery of the event instead of submitting a written LER. Because plant conditions necessary to prompt a containment isolation were not present, this event constitutes an invalid system actuation under 10 CFR 50.73(a)(2)(iv)(A). The condition meets the criteria of 10 CFR 50.73(a)(2)(iv)(B)(2) because the loss of the Unit 1 'B' RPS bus affected containment isolation valves in more than one system.

"On 1/4/2010 at 1418 hours, the Unit 1 'B' RPS bus was lost. This event resulted in a half scram and primary containment isolations. By design, when the RPS MG set output breaker trips, all EPA breakers downstream of the MG set also trip resulting in a half scram and primary containment isolation signals.

"An event investigation found the Unit 1 'B' RPS MG set running with its output breaker tripped. The output voltage was indicating 120VAC, which indicates that the voltage regulator was operating properly. Upon removal of the MG set cover, the underfrequency relay (UFR) contacts were found to be chattering, with frequency steady at approximately 60 Hz. A review of plant drawings indicated that a chattering UFR could cause the MG set output breaker to trip. Voltage readings were taken and no additional electrical problems (other than the UFR) were identified. The affected RPS loads were subsequently powered from their alternate source and all actuations and isolations were reset.

"Inspection and test of the failed UFR found that one leg of a capacitor on the UFR electronic board had broken adjacent to its solder joint connection on the board. It is suspected that the capacitor lead may have been flawed during manufacture of the board. The failure was accelerated by the constant vibration that the connection is subjected to, as the UFR is mounted on the MG set.

"The failed UFR electronic board was subsequently replaced and successfully passed all functional tests.

"There were no actual safety consequences associated with this event. Valves affected by the invalid signal fulfilled their isolation function by successfully closing. The RPS loads were transferred to their alternate power supply and the trips and isolations were reset. In addition, the Unit 1 'B' RPS bus did not experience an underfrequency condition."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 45728
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: JOE BENNETT
HQ OPS Officer: JOE O'HARA
Notification Date: 02/25/2010
Notification Time: 23:37 [ET]
Event Date: 02/25/2010
Event Time: 19:35 [CST]
Last Update Date: 02/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BRIAN BONSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 95 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO RHR INOPERABILITY

"At 1840 on 2/25/10, Unit 2 RHR Division II became inoperable due to exceeding 260 degrees F on the injection line. The temperature is elevated due to leakage past the injection line check valve (2-CKV-74-68) and the inboard injection valve (2-FCV-74-67). The 260 degree F value is based on engineering calculations to ensure the injection line does not become steam voided. RHR Division I was already inoperable for scheduled maintenance when this condition occurred. Entered TS LCO 3.0.3 based on TS LCO 3.5.1 Condition H - Two or more Low pressure ECCS injection/spray subsystems inoperable for reasons other than Condition A.

"Action was taken to lower power at 1935 when the conditions requiring entry into LCO 3.0.3 could not be corrected.

"Tech Spec LCO 3.0.3 was exited at 2000 when RHR Loop II system pressure was raised using an alternate keep fill flow path to ensure that the injection line would remain filled. Power will be returned to 100%.

"This event requires a 4 hour report in accordance with 10 CFR 50.72(b)(2)(i)."

The licensee informed the NRC Resident Inspector.

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Thursday, March 29, 2012