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Event Notification Report for December 4, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/03/2009 - 12/04/2009

** EVENT NUMBERS **


45413 45530 45532 45537

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Fuel Cycle Facility Event Number: 45413
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: CALVIN PITTMAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/05/2009
Notification Time: 15:55 [ET]
Event Date: 10/04/2009
Event Time: 15:00 [CDT]
Last Update Date: 12/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(1) - UNPLANNED CONTAMINATION
Person (Organization):
MIKE ERNSTES (R2DO)
DENNIS DAMON (NMSS)

Event Text

UNPLANNED CONTAMINATION DURING STARTUP

"On 10/04/2009 at 1500 C-331 unit 2 cell 2 was being charged and placed on stream and had just gone above atmospheric pressure when a Maintenance Mechanic observed smoke coming from the cell instrument cubicle and determined it to be UF6 outleakage from cell process instrumentation. To stop the release the cell was immediately taken back below atmospheric pressure. Investigation revealed that a UF6 release had occurred inside the instrument cubicle. The amount of material released has not yet been determined. Decontamination is underway but has not been completed inside the cabinet. The area outside the cabinet has been decontaminated. No injuries or personnel exposure occurred as a result of this event. This is being reported based on 10 CFR 76.120(c)(1)(i) (unplanned contamination event).

"PGDP Problem Report Nos. ATRC-09-2435; PGDP Event Report No. PAD-2009-016. Responsible Division: Operations

"PGDP Assessment and Tracking Report No. ATR-09-2435; PGDP Event Report No. PAD-2009-16; Worksheet No. Responsible Division: Operations

"The NRC Senior Resident Inspector has been notified of this event."

Decontamination is expected to be completed on 10/6/2009.

* * * RETRACTION FROM CALVIN PITTMAN TO VINCE KLCO ON 12/03/09 AT 1551 EST* * *

"After further review, it was determined that the amount of contamination was significantly less than five times the lowest annual limit on intake specified in Appendix B to Section 20.1001-20.2402 of 10CFR20 for the material."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (Guthrie) and NMSS (Whaley).

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Power Reactor Event Number: 45530
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: ROBERT MATUSZAK
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/01/2009
Notification Time: 11:08 [ET]
Event Date: 12/01/2009
Event Time: 12:00 [EST]
Last Update Date: 12/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
KENNETH RIEMER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 99 Power Operation

Event Text

IPCS SYSTEM OOS FOR SECURITY MODIFICATION

"Beginning December 1,2009, at approximately 1200, the Fermi 2 Integrated Plant Computer System (IPCS) will be removed from service to support installation of a Cyber Security Modification. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the PCS platform and will be out of service when the PCS is removed from service. These systems will be unavailable to the Control Room and all other Emergency Response Facilities (ERFs) for approximately six hours. By 1800, it is planned to restore IPCS, including SPDS and ERDS, to the Control Room, Operational Support Center, and the Technical Support Center. The IPCS will remain unavailable to the Emergency Operations Facility (EOF) as well as alternate EOF. On December 2, at approximately 1600, IPCS will be restored to the EOF but will remain unavailable to the alternate facilities. On December 3, 2009, at approximately 1600, IPCS will be restored, including alternate facilities.

"During this entire duration dose assessment capability will only be available in the manual data input mode. A follow-up notification will be submitted when the PCS is completely restored. For the first six hours of the PCS outage, the emergency assessment capability of all Fermi 2 ERFs will be degraded by the loss of IPCS and SPDS. During this period the ERDS function will also be lost. For the following 24 hrs., the EOF will have no IPCSs capability, which includes the SPDS function. Based on the aggregate effect of these losses, this notification is being made per the requirements of 8 Hour Non-Emergency Notification 10CFR,50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."

The licensee will notify the NRC Resident Inspector.

* * * UPDATE AT 1753 EST ON 12/3/09 FROM MATUSZAK TO HUFFMAN * * *

"On December 3, 2009, at 1530, emergency assessment capability has been restored to all on site emergency response facilities."

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

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General Information or Other Event Number: 45532
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ECS-TEXAS LLP
Region: 4
City: AUSTIN State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/01/2009
Notification Time: 14:45 [ET]
Event Date: 02/04/2008
Event Time: 10:00 [CST]
Last Update Date: 12/01/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICK DEESE (R4DO)
BILL VONTILL (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGED NUCLEAR GAUGE NOT INITIALLY REPORTED

The following report was received via e-mail:

"On Monday, February 4, 2008, a technician was attempting to load a gauge on a truck when he dropped the gauge on the tailgate whereupon the index probe broke off and the Cs-137 probe became extended and failed to retract to the shielded position. The gauge was then loaded into the cab of the truck and was delivered to the local site office less than ten minutes from the work site. A service company was notified and within an hour, the source rod was safely retracted into the shielded position. The gauge sources were satisfactory leak tested. No overexposures occurred in this event. The licensee required all gauge users to attend refresher training on nuclear gauge safety and procedures. The licensee was cited for a related violation.

"During a record review, it was discovered that this event was reported to the NRC using the Nuclear Materials Event Database (080192) instead of to the Headquarters Operations Officer.

"Texas Incident #: I-8494"

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Power Reactor Event Number: 45537
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [ ] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAVID OAKES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/03/2009
Notification Time: 09:14 [ET]
Event Date: 12/03/2009
Event Time: 04:30 [MST]
Last Update Date: 12/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RICK DEESE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP AFTER LOSS OF INSTRUMENT AIR TO CONTAINMENT

"On December 3, 2009 at approximately 04:30 Mountain Standard Time (MST) Palo Verde Unit 3 operators manually tripped the reactor from approximately 100% rated thermal power due to loss of Instrument Air (IA) to Containment. This loss was apparently caused by a failure (closed) of the outboard IA Containment Isolation Valve (CIV) solenoid valve. Loss of IA to Containment resulted in closure of the inboard Reactor Coolant Pump (RCP) controlled seal bleedoff CIV. The RCP seal bleedoff was then being diverted via relief valve to the Reactor Drain Tank (RDT) inside Containment.

"Following the manual reactor trip all CEAs [Control Element Assemblies] fully inserted into the reactor core. All 4 RCPs were stopped to allow for isolation of bleedoff to the RDT. Upon completion of Standard Post Trip Actions, the crew entered the Optimal Recovery Procedure for Loss of Forced Circulation. No emergency classification was required per the Emergency Plan. No automatic ESF actuations occurred and none were required. Safety related buses remained energized during and following the reactor trip. The Emergency Diesel Generators did not start and were not required. The offsite power grid is stable. LCO 3.6.3 was entered due to failure of the IA CIV. No major equipment was inoperable prior to the event which contributed to the need for manual reactor trip."

The reactor was manually tripped for equipment preservation. No safety or relief valves lifted other than noted above. After the trip, decay heat was being removed using the turbine bypass valves and steam generator level was being maintained with the auxiliary feedwater pumps. The licensee also entered LCO 3.4.5, "RCS Loop Operability" because the RCPs were stopped.

The licensee notified the NRC Resident Inspector.

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