|
Home > Electronic Reading Room > Document Collections > Reports Associated with Events
> Event Notification Reports
> 2006
> September 22
Event Notification Report for September 22, 2006
|
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/21/2006 - 09/22/2006
** EVENT NUMBERS **
|
| Power Reactor |
Event Number: 42852 |
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MARK COVEY
HQ OPS Officer: JOHN MacKINNON
|
Notification Date: 09/21/2006
Notification Time: 12:20 [ET]
Event Date: 09/08/2006
Event Time: 10:15 [CDT]
Last Update Date: 09/21/2006
|
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
|
Person (Organization):
BLAIR SPITZBERG (R4)
PAT GWYNN (R4)
MIKE WEBER (NRR)
MELVYN LEACH (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 |
Event Text
DISCOVERY OF AFTER-THE-FACT EMERGENCY CONDITION: INAPPRORIATE CHANGE MADE TO EMERGENCY ACTION LEVEL 3J BACK IN 1997 CAUSED AN EMERGENCY, ALERT, NOT TO BE DECLARED.
"On 9/08/2006 at 1015 during painting activities in a safety-related area the Methanol Short Term Exposure Limit was exceeded. In accordance with Callaway Plant procedures the location was determined to contain a Hazardous ATMOSPHERE. Subsequently, Callaway Plant Emergency Action Levels (EAL) were reviewed and it was determined that the event did not meet the EAL criteria for Callaway Plant EAL 3J related to release of flammable or toxic gases in a safety - related area.
"On 9/21/2006 following a debrief that was conducted by Region IV NRC personnel, it was determined at 1025 that an inappropriate change to the intent of EAL 3J was made in 1997. As a result of this discussion, it was determined that an Alert should have been declared in accordance with plant EAL 3J.
"Per guidance given in NUREG 1022, Revision 2, Section 3.1.1. "Immediate Notifications", an ENS notification is being made within one hour of discovery of the event. No actual declaration of the emergency class will be made since the event has been concluded and the basis for the emergency no longer exists.
"The NRC Resident Inspector has been notified." Licensee also notified State, Local Officials and other government agencies. |
| Power Reactor |
Event Number: 42854 |
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID O'DONNELL
HQ OPS Officer: JASON KOZAL
|
Notification Date: 09/21/2006
Notification Time: 20:13 [ET]
Event Date: 09/21/2006
Event Time: 18:15 [EDT]
Last Update Date: 09/21/2006
|
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
|
Person (Organization):
JULIO LARA (R3)
MARY JANE ROSS-LEE (NRR)
|
| 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
OSCILLATION POWER RANGE MONITORS (OPRMS) INOPERABLE
"On September 14, 2006, the Plant Staff was notified by General Electric (GE) via a draft Safety Communication SC06-010 of a potential non-conservative setting of the OPRM Enabled Region Drive Flow Setpoint when the plant is in Single Reactor Recirculation Loop Operations. On September 21, 2006, at 1815 hours, based on available information, it was conservatively determined that all four OPRM channels were inoperable due to their current flow setpoint settings and uncertainties associated with OPRM enabling.
"The OPRM instrumentation provides inputs to the Reactor Protection System. The OPRM instrumentation is relied upon for providing a safe shutdown safety function when operating during an unstable power to flow condition. Operations personnel entered Technical Specification LCO 3.3.1.3 Action B.1 to initiate an alternate method to detect and suppress thermal hydraulic instability oscillations.
"This event is being reported as a condition that could have prevented the safety function of structures or systems required to shut down the reactor and maintain it in a safe shutdown condition. These actions and this report are based on preliminary information. Updates will be provided as necessary as additional information becomes available."
The licensee notified the NRC Resident Inspector. |
|
