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Event Notification Report for June 12, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/11/2007 - 06/12/2007

** EVENT NUMBERS **


43331 43394 43411 43416

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 43331
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BRIAN HUPKE
HQ OPS Officer: JOE O'HARA
Notification Date: 05/01/2007
Notification Time: 00:39 [ET]
Event Date: 04/30/2007
Event Time: 20:17 [CDT]
Last Update Date: 06/11/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHRISTINE LIPA (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 98 Power Operation 98 Power Operation

Event Text

HPCI DECLARED INOPERABLE DUE TO PRIMARY CONTAINMENT NITROGEN LEAK

"At 1007 on the morning of 04/30/2007, operations personnel identified an adverse trend in Primary Containment Nitrogen makeup frequency. The subsequent investigation determined that Primary Containment Nitrogen was leaking backwards thru V22-0017 HPCI Turbine Exhaust Line Stop-Check Valve and V22-0016 HPCI Exhaust Check Valve, via the HPCI exhaust vacuum breakers and the environment of the HPCI room via the turbine seals.

"The degradation of V22-0016 and V22-0017 constitute a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. (50.72(b)(3)(v)(D)).

"At 2017 on the evening of 04/30/2007, V22-0017 HPCI Turbine Exhaust Line Stop-Check Valve and V22-0016 HPCI Exhaust Check Valve were declared inoperable due to Primary Containment Nitrogen leakage as described above.

"At 2032 on the evening of 04/30/2007, V22-0017 HPCI Turbine Steam Exhaust Line Isolation was shut to isolate Primary Containment Nitrogen leakage.

"With V22-0017 shut, HPCI is INOPERABLE and Unavailable."

The licensee is in a 14 day LCO under section 3.6.1.3 for Primary Containment Isolation Valves (PCIV). However, they are in a 72 hour LCO for having "A" core spray and HPCI inoperable, concurrently. The licensee expects to have "A" core spray restored during dayshift on 5/1/07. Additionally, the licensee is in a 7 day LCO for EDG OOS.

The licensee notified the NRC Resident Inspector.

* * * UPDATE PROVIDED BY E. VANN TO J. KOZAL ON 5/01/07 AT 1048 * * *

The licensee provided a correction to the TS LCO statement referenced in the initial report. The 14 day LCO is not under section 3.6.1.3 for Primary Containment Isolation Valves (PCIV). The correct LCO statement is 3.5.1 for ECCS Operating.

The licensee will notify the NRC Resident Inspector. R3DO (Lipa) notified.

* * * RETRACTION PROVIDED BY ROBERT MURRELL TO P. SNYDER ON 6/11/07 AT 1511 * * *

"The purpose of this notification is to retract a previous report made on 5/01/07 at 0039 (ET) (EN 43331). Notification of this issue to the NRC on 5/01/07 was initially made due to the High Pressure Coolant Injection (HPCI) system being declared inoperable due to a primary containment nitrogen leak.

"Specifically, at the time, operations personnel identified an adverse trend in Primary Containment Nitrogen makeup frequency. The subsequent investigation determined that Primary Containment Nitrogen was leaking backwards thru V22-0017, HPCI Turbine Exhaust Line Stop-Check Valve, and V22-0016, HPCI Exhaust Check Valve, via the HPCI exhaust vacuum breakers and the environment of the HPCI room via the turbine seals.

"Since the initial report, Engineering has determined that the HPCI system was capable of performing its safety function.

"This conclusion is based on the fact that V22-0016 and V22-0017 open during HPCI operation and the closing function is no longer included in the 10CFR50 Appendix J Testing Program since the line does not constitute a potential primary containment atmospheric pathway during and following a Design Basis Accident (DBA). MO2290A and MO2290B (HPCI Turbine Steam Exhaust Vacuum Breaker motor operated valves), which are Appendix J Program valves, communicate with both the HPCI exhaust line and the torus air space and will isolate during a Design Basis Accident (DBA). Therefore, the HPCI injection was still operational and the HPCI exhaust line will not communicate directly with the containment atmosphere and will not provide a containment atmospheric pathway during and following a Design Basis Accident.

"All safety design functions of V22-0016 and V22-0017 were met. Additionally, as-left valve closure testing on both V22-0016 and V22-017 were successful and both valves were fully operable.

"This event is not considered a Safety System Functional Failure and is not reportable to the NRC as a Licensee Event Report per 10 CFR 50.73."

The licensee notified the NRC Resident Inspector. Notified R3DO (A.M. Stone).

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Power Reactor Event Number: 43394
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: LANCE LANE
HQ OPS Officer: JOE O'HARA
Notification Date: 05/29/2007
Notification Time: 10:09 [ET]
Event Date: 05/29/2007
Event Time: 08:08 [CDT]
Last Update Date: 06/11/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHUCK CAIN (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

SAFETY PARAMETER DISPLAY SYSTEM (SPDS) REMOVED FROM SERVICE FOR COMPUTER UPGRADE

"On 05/29/2007 at 08:08 am CDT, the Wolf Creek Nuclear Plant Information System (NPIS) was removed from service for a planned computer system upgrade. The system upgrade will result in the SPDS and Emergency Response Data System (ERDS) being inoperable for approximately three weeks.

"Wolf Creek Nuclear Operating Corporation is making this ENS notification pursuant to the criteria of 10 CFR 50.72(b)(3)(xiii). There is no other loss of emergency assessment capability concurrent with the removal of the NPIS from service. Plant personnel entered the appropriate Off-Normal procedure and will obtain local readings for the equipment that is normally monitored by SPDS and NPIS during the plant computer upgrade.

"The Senior NRC Resident has been briefed on this evolution and the planned return to service of the system."

* * * UPDATE FROM LANE TO SNYDER AT 1802 EDT ON 6/11/07 * * *

"On 06/09/07 at 18:46 CDT, the Wolf Creek Nuclear Plant Information System (NPIS) was returned to service following the computer upgrade. This restored the Safety Parameter Display System (SPDS) to OPERABLE and made the Emergency Response Data System (ERDS) available for use. The ERDS system will not be considered OPERABLE until testing has been performed with the NRC to confirm proper data transmissions.

"Some data points and processes are still being tested prior to being returned to service."

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

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General Information or Other Event Number: 43411
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: METCO
Region: 4
City: LAKE CHARLES State: LA
County:
License #: LA-8043-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/06/2007
Notification Time: 12:36 [ET]
Event Date: 05/08/2007
Event Time: [CDT]
Last Update Date: 06/07/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL SHANNON (R4)
GREG MORELL (FSME)

Event Text

AGREEMENT STATE REPORT INVOLVING EQUIPMENT FAILURE OF RADIOGRAPHY CAMERA

The following report was received from the Louisiana Department of Environmental Quality (LA DEQ) via fax:

"[A] field inspection was performed on a field crew for METCO. [While] performing the inspection a misconnect test was performed. The crank outs had a serial number of MST 225 manufactured by AEA Technologies and the camera was an Amersham 880 Sigma with serial number S1712. This misconnect test failed. The crank outs were removed [from] operation and taken back to the shop. The problem was located on the crank out and was repaired. A misconnect test was then performed with the same camera and an additional camera and it passed the test. METCO stated that they will pay closer attention to damage and wear and tear on equipment."

LA Event Report ID No.: LA070014

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Power Reactor Event Number: 43416
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MATT EVANS
HQ OPS Officer: JASON KOZAL
Notification Date: 06/11/2007
Notification Time: 01:17 [ET]
Event Date: 06/10/2007
Event Time: 20:03 [CDT]
Last Update Date: 06/11/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MONTE PHILLIPS (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 97 Power Operation 97 Power Operation

Event Text

HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE DUE TO FAILED INVERTER

"At 2003 on 6/10/07, the division 3 Nuclear System Protection System (NSPS) inverter power supply failed for unknown reasons. As a result of this failure, the High Pressure Core Spray (HPCS) system has been declared inoperable. This is a failure of a single train safety system and is reportable under 10 CFR 50.72(b)(3)(v)(D). Troubleshooting has been initiated to determine the cause of this failure."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012