Event Notification Report for December 12, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/09/2005 - 12/12/2005

** EVENT NUMBERS **


42193 42194

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Power Reactor Event Number: 42193
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NED DENNIN
HQ OPS Officer: PETE SNYDER
Notification Date: 12/09/2005
Notification Time: 13:15 [ET]
Event Date: 12/09/2005
Event Time: 09:01 [EST]
Last Update Date: 12/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RONALD BELLAMY (R1)

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

TRIP OF A STARTUP BUS BREAKER RESULTS IN START OF EMERGENCY DIESEL GENERATORS

"At 0901 on December 9, 2005, a trip of the 10 Startup Bus Breaker occurred at Limerick Generating Station in the 220 KV substation. This de-energized one of the required offsite sources and the associated 10 Startup Bus and 101 Safeguard Bus, causing a valid actuation signal for the D11, D13, D22 and D24 Diesel Generators. All diesels started and their associated 4 KV buses swapped to the 201 Safeguard Bus as required. The cause of the 10 Startup Bus Breaker trip is under investigation. Units 1 and 2 remain at 100% power."

No safety related loads were lost. The diesel generators were still running at the time of the call but, the licensee was shutting down the diesels per procedure.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42194
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE PHILLIPS
HQ OPS Officer: PETE SNYDER
Notification Date: 12/09/2005
Notification Time: 18:11 [ET]
Event Date: 12/09/2005
Event Time: 15:44 [EST]
Last Update Date: 12/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JAY HENSON (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Standby 0 Hot Standby

Event Text

RCS PRESSURE BOUNDARY LEAKAGE IDENTIFIED

"At 1450 hours on 12/5/05, Unit 2 entered abnormal operating procedure 18004-C 'RCS Leakage' due to increasing containment atmospheric radiation levels as identified on 2RE2562A. Per procedure, an RCS leak rate determination was commenced and completed as of 1629 hours, 12/8/05 (identified = 0.032gpm, unidentified = 0.254gpm, total = 0.286gpm). While making preparations for a containment entry for leakage inspection, a second leak rate [determination] was completed at 2020 hours, 12/8/05 (identified = 0.070gpm, unidentified = 0.267gpm, total = 0.337gpm). At 2240 hours, 12/8/05, the team performing the containment leak inspection reported no leakage identified outside the bioshield. Another leak rate [determination] was completed at 0245 hours, 12/9/05, the team performing the containment leak inspection reported that by using a robotic camera, water was observed coming down the inside wall of the bioshield in the area of loop 2. At 0433 hours, 12/9/05, a shutdown of Unit 2 was initiated to allow further investigation / repair of the RCS leak inside containment. Unit 2 was placed in Mode 3 at 1313 hours, 12/9/05. At 1544 hours, 12/9/05, the containment leak inspection team reported pressure boundary leakage at a welded connection where a 3/4 inch bypass line is welded to the RCS loop upstream of the RHR loop suction valve 2HV8701B. [Plant Vogtle personnel are] presently preparing to commence shutdown to Mode 5 for repair of the leak."

Technical specification 3.4.14 applies and requires no pressure boundary leakage. The plant is currently removing decay heat by steaming from the steam generators through the steam dump valves to the condenser. All safety related electrical buses are available. Emergency diesel generators are available and in standby.

The licensee notified the NRC Resident Inspector.

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