| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/27/2009 - 03/30/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44933 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: WELD SPEC, INC
Region: 4
City: BEAUMONT State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/25/2009
Notification Time: 12:05 [ET]
Event Date: 03/25/2009
Event Time: 09:40 [CDT]
Last Update Date: 03/27/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - POSSIBLE OVEREXPOSURE OF EMPLOYEE
"On March 25, 2009, at 0940, the State of Texas was notified by a licensee that they had received a report from their dosimetry processor indicating that one of their employees had received greater than 1000 rad exposure for the month of February, 2009. The exposure record provided did not indicate whether the exposure was static or dynamic. The Radiation Safety Officer (RSO), who started this position in the first part of March, 2009, contacted the radiographer. The radiographer stated that she had not performed any operations with a radiography camera because she had hurt her knee. The radiographer stated that she had worked nine jobs, and all her work was done in the dark room. The RSO has made arrangements for the radiographer to have blood work done today, 3/25/09. The RSO stated that she had two other individuals who had received higher than normal readings but had not exceeded any limits. These individuals were reassigned to duties that will limit their exposure.
"An Agency (state) investigator contacted the radiographer and asked her when in the month of February she had started wearing her badge. She stated that she began wearing the badge in the middle of February. She stated that she picked it up from a mail box at the company's office. She stated that she carried the badge with her in [her] lunch box when she was not wearing it and that no one else would have had access to the badge from this point on.
"She stated that no source disconnects had occurred at any of the work sites she was at in the month of February. She stated that she does not know how her badge could have received that much exposure, but she is sure she had not received that much exposure. She stated that she felt fine. Additional information will follow as it is received."
Texas Incident Number: I-8622
* * * UPDATE FROM ART TUCKER TO PETE SNYDER AT 1218 ON 3/27/09 * * *
"The state received a fax which contained a copy of the blood work done on 3/26/09 for the individual involved from the licensee. Also included in the fax was a copy of blood work that was done on the individual on 2/25/09 prior to a medical procedure. Both samples returned very similar results and were considered normal by her physician."
Notified R4DO (O'Keefe) and FSME (McIntosh). |
| Power Reactor | Event Number: 44937 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: EDWARD McCUTCHEN JR.
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/26/2009
Notification Time: 18:52 [ET]
Event Date: 03/27/2009
Event Time: 00:00 [CDT]
Last Update Date: 03/27/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NEIL OKEEFE (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 TROUBLESHOOTING EMERGENCY OFFSITE FACILITY COMMUNICATIONS
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) as an event that will result in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g. significant portion of control room indication, Emergency Notification System or offsite notification system.)
"At approximately 0000 on 3/27/09, all five of the T-1 data lines to the Emergency Offsite Facility (EOF) will be taken out of service to troubleshoot and repair malfunctioning phone company equipment. Multiple short duration outages will occur until the malfunction can be located and repaired. This outage will cause a loss of Plant Management Information System printer capability, Safety Parameter Display System (SPDS) capability, FTS 2001 system, Alternate Intercom system, Low Band base radio (the primary Downwind Survey team radio), State Notification Telephone System, Dose Assessment and some external phone lines at the EOF. This loss of capability affects only the off-site EOF. All other emergency communications from the site to the NRC are not affected.
"Compensatory measures being put into effect include SPDS information relayed via telephone from the Technical Support Center, dose assessment and offsite notifications and reports via alternate means, or relocate the on-call Emergency Director to the Control Room and make notifications to offsite agencies via the Control Room Communicator. CNS is in contact with communications personnel to restore the T-1 lines as quickly as possible in the event of a declared emergency.
"Region IV and the NRC Resident Inspector were notified of the planned loss of the T-1 lines. CNS will notify the NRC when all EOF equipment affected by the T-1 lines have been satisfactorily tested and verified to be operational."
* * * UPDATE ON 3/27/09 AT 1405 FROM STEVE WHEELER TO MARK ABRAMOVITZ * * *
"This notification is an update to EN#44937 regarding the planned troubleshooting of Emergency Off Site Facility (EOF) communications equipment. Discussion with the NPPD telecommunications vendor have identified that the planned troubleshooting and repair of Cooper's EOF communications equipment was completed non-intrusively. There was no actual interruption of the EOF communications equipment. Testing by the vendor, NPPD Telecommunications Department personnel and NPPD Emergency Preparedness Department personnel has been completed and all EOF communications equipment has been verified to be fully functional. The NRC Senior Resident Inspector and the State and Local Agencies will be notified that the CNS EOF communications equipment is fully functional."
Notified the R4DO (O'Keefe). |
| Power Reactor | Event Number: 44940 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [ ] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: DAVE FOSS
HQ OPS Officer: JASON KOZAL | Notification Date: 03/27/2009
Notification Time: 08:40 [ET]
Event Date: 03/02/2009
Event Time: 11:55 [EDT]
Last Update Date: 03/27/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
JAMES DWYER (R1)
|
| 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 INVALID PRIMARY CONTAINMENT ISOLATION SIGNAL DUE TO MAINTENANCE ERROR
"This 60-day report, as allowed by 10 CFR 50.73(a)(1), is being made under the reporting requirement in 10CFR50.73(a)(2)(iv)(A) to describe an unplanned, invalid actuation of specified systems, specifically the Unit 3 Primary Containment Isolation System (PCIS). On 3/2/09, at approximately 1155 hours, Unit 3 experienced an invalid PCIS partial isolation. Associated with the momentary shorting of a terminal lead during maintenance, a fuse was blown and power was lost to nine Primary Containment Isolation Valves (PCIVs). This resulted in two of the PCIVs re-positioning to the closed position. The re-positioned PCIVs were the AO-3-07B-3509 (Inner Drywell Exhaust Valve) and the AO-3-16-5235 (Instrument Nitrogen System Suction Valve). Closure of these valves affected the Containment Atmospheric Control (CAC), Containment Atmospheric Dilution (CAD) and Containment Instrument Nitrogen systems. Closure of these valves was the expected response for loss of power to this portion of the PCIS control circuitry. The fuse was replaced and the valves were restored to an operable condition by 1235 hours on 3/2/09.
"The invalid PCIS isolation was a result of the momentary shorting of an energized terminal lead associated with preventive maintenance to replace a pressure switch associated with PCIV AO-3-07B-3519 (Nitrogen Supply Purge Valve).
"This issue has been entered into the site Corrective Action Program (CR 887441) for evaluation and implementation of further corrective actions. The NRC resident has been informed of this notification." |
| Power Reactor | Event Number: 44942 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: G. MILLER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/28/2009
Notification Time: 03:45 [ET]
Event Date: 03/28/2009
Event Time: 01:46 [EDT]
Last Update Date: 03/28/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
HIRONORI PETERSON (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 24 | Power Operation | 0 | Hot Shutdown | Event Text REACTOR SCRAM DUE TO MODE SWITCH BEING PLACED IN SHUTDOWN FOLLOWING HIGH VIBRATION ON MAIN TURBINE #1 BEARING
"At 0146 EDT 3/28/09, the reactor mode switch was taken to shutdown in response to high vibration levels on the Main Turbine #1 bearing. Reactor power was at its reduced level in preparation for entry into Refueling Outage #13 which was scheduled to begin at 0300 EDT. All control rods fully inserted into the core. The lowest reactor vessel water level reached was 162 inches. HPCI & RCIC did not initiate. No safety relief valves (SRV) actuated. Reactor water level is being controlled in the normal band using the Control Rod Drive (CRD) system. All isolations and actuations for reactor vessel water level 3 occurred.
"The cause of the high main turbine vibrations is currently under investigation. There was no maintenance or testing in progress that would explain the high turbine vibration levels. At the time of the scram all ECCS systems and Emergency Diesel Generators were operable. This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B), any event that results in actuation of the reactor protection system (RPS) when the reactor is critical."
The Licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44943 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NORA GRANETO
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/29/2009
Notification Time: 20:18 [ET]
Event Date: 03/29/2009
Event Time: 18:25 [EDT]
Last Update Date: 03/29/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
JAMES DWYER (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text POTENTIALLY CONTAMINATED PERSON SENT OFFSITE FOR HOSPITAL EVALUATION
"A worker performing U2 outage activities was exhibiting signs of heat stress and dizziness when exiting the U2 drywell access control point. Offsite medical assistance was requested and the worker was transported to the Pottstown Memorial Medical Facility as a potentially contaminated person. The ambulance left the site at 1825 hours 3-29-09. At 1845 hours while at the Pottstown Memorial Medical Facility it was determined that the worker was NOT contaminated. This report being submitted via the requirements of 10CFR50.72 (b)(3)(xii)."
The individual was performing routine valve operations and was a plant employee.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44944 | Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE CHRISTOPHER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/30/2009
Notification Time: 09:35 [ET]
Event Date: 03/30/2009
Event Time: 02:55 [EDT]
Last Update Date: 03/30/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
STEVEN VIAS (R2)
MJ ROSS-LEE (NRR)
ANTHONY McMURTRAY (IRD)
|
| 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 | N | 0 | Refueling | 0 | Refueling | Event Text NOTIFICATION TO OTHER GOVERNMENT AGENCY OF ON-SITE FATAL HEART ATTACK
A licensee employee, working in the Outage Command Center (office environment), which is located inside the Protected Area, had symptoms of a heart attack. On-site emergency personnel responded and the individual was transported off-site to Piedmont Medical Center. Piedmont Medical Center notified the licensee at 0445 hours that the heart attack was fatal.
The licensee notified OSHA.
The licensee does not plan to make a media or press release.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1453 EDT ON 03/30/09 FROM STEVE CHRISTOPHER TO S. SANDIN * * *
"This notification is being made to supplement today's 0935 [EDT] notification. The offsite notification to OSHA occurred at 0847 [EDT], placing the 0935 [EDT] notification to the NRC within the 4 hours required by 10 CFR 50.72 (b)(2)."
The licensee informed state/local agencies and the NRC Resident Inspector. Notified R2DO (Vias). | |