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Event Notification Report for May 11, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/10/2007 - 05/11/2007

** EVENT NUMBERS **


43352 43354 43355

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General Information or Other Event Number: 43352
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: NONDESTRUCTIVE AND VISUAL INSPECTION
Region: 4
City:  State: LA
County:
License #: LA-5601-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/08/2007
Notification Time: 15:40 [ET]
Event Date: 05/04/2007
Event Time: [CDT]
Last Update Date: 05/08/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4)
GREG MORELL (FSME)

Event Text

AGREEMENT STATE REPORT - LOUISIANA - WORKER OVEREXPOSURE

The State provided the following information via facsimile:

"[A licensee representative] with Nondestructive and Visual inspection notified the Louisiana Department of Environmental Quality on May 4, 2007 of an overexposure. The indicated exposure from the badge reading is 5123 mrem. Additional information will be forwarded once it is received."

Louisiana Event Report ID No.: LA070011

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Power Reactor Event Number: 43354
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GARY MERKA
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/10/2007
Notification Time: 15:22 [ET]
Event Date: 03/12/2007
Event Time: 20:27 [CDT]
Last Update Date: 05/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
VINCENT GADDY (R4)

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

Event Text

INVALID TUBINE DRIVEN AUXILIARY FEEDWATER PUMP STARTS

"This report describes three invalid actuations of the Unit 2 Turbine Driven Auxiliary Feedwater (TDAFW) pump that occurred on March 12,2007. This report is being made in accordance with 10CFR50.73(a)(1), which states, in part, 'In the case of an invalid actuation reported under 10CFR50.73(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.'

"On March 12, 2007 at 2027, while performing operator rounds, Operations personnel heard a venting noise coming from the vicinity of the Main Steam Line 2-04 to Auxiliary Feedwater Pump Turbine Steam Supply Valve. One of the Operators put his hand close to the exhaust pilot valve, restricting the venting air flow, which increased the sensing pressure on one of the valve's ports. The valve swapped, exhausting the diaphragm. This caused the TDAFW steam supply valve to fail open and the TDAFW pump started and reached full flow. Operations responded to the event by manually running back the Main Turbine load to 1100 Mew to ensure Reactor Power remained less than 100%. The TDAFW pump was secured and the steam supply valve hand switch was placed in AUTO.

"At 2056, an I&C technician was leak checking the valve actuator and tubing joints. The I&C technician got within close proximity of the Main Steam Line 2-04 to Auxiliary Feedwater Pump Turbine Steam Supply Valve and restricted the venting air flow, which increased the sensing pressure on one of the exhaust pilot valve's ports. The pilot valve swapped, exhausting the diaphragm. The TDAFW Steam Supply Valve failed open again and the TDAFW pump started a second time and reached full flow.

"At 2100, Shift Operations placed the steam supply valve in pullout and declared the TDAFW inoperable. To prevent further inadvertent starts, Operations decided to close the upstream isolation valve. While in the process of closing the isolation valve, the Operator heard air venting from the vicinity of the Main Steam Line 2-04 to Auxiliary Feedwater Pump Turbine Steam Supply Valve. The Operator put his hand under the exhaust pilot valve such that the air flow was restricted, which increased the sensing pressure on one of the valve's ports. The pilot valve swapped, exhausting the diaphragm. The TDAFW steam supply valve failed open again and the TDAFW pump started a third time. Since the upstream isolation valve was partially closed, the TDAFW pump only reached a partial flow of 235 gpm. Shift Operations initiated a clearance to prevent further inadvertent TDAFW pump starts and a work order was initiated to determine the failure mechanism. On March 13, 2007 at 2223, Shift Operations declared the TDAFW pump operable.

"The specific train and system that actuated was the third AFW train on Unit 2. During each of the three TDAFW pump starts, the system started and functioned correctly. During the first two pump starts, the train actuation was complete. As described above, on the third start the train actuation was partial due to less than full flow being developed.

"The second and third TDAFW pump starts took place during trouble shooting and clearance isolation activities, respectively, which occurred prior to the cause being identified. The three AFW invalid actuations occurred due to incorrect setup of the exhaust pilot valve for the Main Steam Line 2-04 to Auxiliary Feedwater Pump Turbine Steam Supply Valve.

"The NRC Resident Inspector will be notified of this report."

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Power Reactor Event Number: 43355
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: KEVIN R BOSTON
HQ OPS Officer: JASON KOZAL
Notification Date: 05/10/2007
Notification Time: 20:16 [ET]
Event Date: 05/10/2007
Event Time: 15:30 [CDT]
Last Update Date: 05/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
VINCENT GADDY (R4)

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

OFFSITE NOTIFICATION DUE TO ELEVATED TRITIUM LEVELS

"On May 7, 2007, a horizontal concrete wall crack at approximately 990 ft 6 inch elevation in a radiologically controlled room located inside the protected area, was observed to have water drops forming on the surface. Samples were collected in enough quantity to perform radiological and chemical analysis. The analysis indicated tritium concentration of 110,000 pCi/L. The limits for tritium in the FCS Off-Site Dose Calculation Manual is 20,000 pCi/L. Based on this analysis a conservative decision to notify the state and local agencies was made on 5/10/2007 at 15:30 CDT per the NEI Ground Water Protection Program. These off-site notifications will be made on 5/11/2007. Further investigation is on-going."

The licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012