| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/22/2003 - 10/23/2003 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40107 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: STEVE NEVELOS
HQ OPS Officer: JOHN MacKINNON | Notification Date: 08/27/2003
Notification Time: 15:22 [ET]
Event Date: 08/27/2003
Event Time: 09:24 [EDT]
Last Update Date: 10/22/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JAMES TRAPP (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 | Event Text CONTROL ROOM ACCESS DOOR LATCH WAS DETERMIEND TO BE NOT FULLY ENGAGING.
At 09:24 am on 08/27/03, a Control Room access door latch was determined to be not fully engaging. The door and latch provide the following functions:
maintain the integrity of the Control Room boundary which is a design feature to maintain Control Room habitability following a design bases accident, and
provide a security barrier to restrict access into the Control Rom complex to only those personnel with preapproved security clearance.
With the latch not engaged, the door was not capable of performing these functions. The appropriate security contingencies were implemented, requiring posting of a Security Force Member at the door controlling access to the Control Room Complex. Technical Specification (TS) 3.0.3 was entered due to the inability of either Control Room ventilation system to maintain Control Room habitability, as required by TS 3.7.2.
At 10:20, the door latch was replaced to re-establish the integrity of the Control Room habitability boundary and TS 3.0.3 was exited. The ability of the latch to properly operate for access and egress was not established; access through the affected door remained restricted until repairs can be completed (there are additional doors to the Control Room that remain fully functional).
At 14:00, the door was again impaired for repair of the door latch. Full functionality of the door was restored at 14:41.
The NRC Resident Inspector was notified of this event by the licensee.
* * * RETRACTION AT 1143 EDT ON 10/22/03 FROM A. BRAEDY TO E. THOMAS * * *
"At the time of the original notification the ability to maintain Control Room habitability, as required by TS 3.7.2 was not assured. Subsequent evaluation has determined that if a postulated accident had occurred during the time that the door latch was impaired, control room dose would be less than the acceptance criteria specified in 10CFR50.67 and Regulatory Guide 1.183 and bounded by our current analysis. The site boundary doses were never affected. The dose impact of the condition as it existed would be bounded by the current analysis. Thus, the safety function would have been fulfilled."
Notified R1DO (L. Doerflein) |
| Power Reactor | Event Number: 40268 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: M. SLIVKA
HQ OPS Officer: JOHN MacKINNON | Notification Date: 10/22/2003
Notification Time: 02:56 [ET]
Event Date: 10/22/2003
Event Time: 01:03 [EDT]
Last Update Date: 10/22/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
CHARLES R. OGLE (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 2 | Startup | 2 | Startup | Event Text HIGH PRESSURE HOSE CONNECTION FAILED RESULTING IN A TRAIN "A" MANUAL STEAM LINE ISOLATION
"Manually initiated a steam line isolation signal upon report of a failed connection on a high pressure hose being used to vent a main steam isolation valve bonnet cavity (to open pressure locked valves). The manual isolation resulted in closure of the four open main steam isolation valves (Train "A"). The isolation was conducted as a preventative measure for personnel protection (three people were in the South Main Steam Valve Room when the fitting failed). No personnel were injured. Plant conditions remained stable."
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 40270 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: Kevin Dahm
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/22/2003
Notification Time: 18:58 [ET]
Event Date: 10/22/2003
Event Time: 16:23 [EDT]
Last Update Date: 10/22/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JAMES CREED (R3)
CYNTHIA CARPENTER (NRR)
RICHARD WESSMAN (IRO)
|
| 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 OFFSITE NOTIFICATION CONCERNING ONSITE FATALITY
"Today at 1623, a report was received in the Control Room of a medical emergency involving a plant employee at the power plant. Onsite personnel responded and paramedics/ambulance arrived onsite.
"We have been informed that the individual died from an apparent heart attack.
"The NRC Resident Inspector has been notified. This report is being made pursuant to 10 CPR 50.72(b)(2)(xi)."
The local news media has broadcasted the event and the licensee does not intend to issue a press release at this time.
The employee was not working in a radioactive contaminated area at the time of the event. | |