| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/20/2005 - 09/21/2005 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 42001 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: GRANT MELIN
HQ OPS Officer: JOHN KNOKE | Notification Date: 09/19/2005
Notification Time: 11:26 [ET]
Event Date: 09/19/2005
Event Time: 11:04 [EDT]
Last Update Date: 09/20/2005 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
JOEL MUNDAY (R2)
ERIC BENNER ()
PETER WILSON (IRD)
EACHES (FEMA)
MIKE INZER (DHS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNUSUAL EVENT DECLARED DUE TO HURRICANE RITA
"Turkey Point nuclear power plant is under a hurricane warning from the National Hurricane Center, starting at 11:00 EDT for Tropical Storm Rita."
On-site facilities are not being activated at this time. No off-site assistance is requested. All 4 Emergency Diesel Generators are available and fully operable if needed. The electrical grid is stable. The licensee has notified the State and local agencies.
The licensee will notify the NRC Resident Inspector.
* * * UPDATE FROM D. FUNK TO W GOTT AT 1917 ON 09/19/05 * * *
Tropical storm force winds are expected between 0700 and 2100 on 09/20/05. Maximum expected sustained wind speed is 53 MPH.
The licensee notified the NRC Resident Inspector.
Notified R2DO (C Ogle) and R2 IRC (J. Hufham)
* * * UPDATE FROM C. MONTGOMERY TO M. RIPLEY 1410 EDT 09/20/05 * * *
"As of 1353 EDT 09/20/05, Turkey Point nuclear power plant is no longer in an Unusual Event due to a hurricane warning from the National Hurricane Center for Hurricane Rita."
The licensee notified the NRC Resident Inspector, and State and County officials . Notified R2 DO (Ogle), IRD Mgr (Wilson), NNR EO (Benner), FEMA (Liggett), HERO (Gott), DHS via DOE Nuclear Event Notification Desk (J. Everett) |
| Power Reactor | Event Number: 42002 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: PAUL DUNDIN
HQ OPS Officer: BILL GOTT | Notification Date: 09/19/2005
Notification Time: 16:25 [ET]
Event Date: 09/19/2005
Event Time: 07:22 [EDT]
Last Update Date: 09/20/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
JOHN WHITE (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 FITNESS FOR DUTY
A licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 9/20/05 TO CORRECT ERROR * * *
The text should read: A non-licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42003 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [ ] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: SARA ANDERSON
HQ OPS Officer: BILL GOTT | Notification Date: 09/20/2005
Notification Time: 12:48 [ET]
Event Date: 09/20/2005
Event Time: 05:00 [EDT]
Last Update Date: 09/20/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
JOHN WHITE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Shutdown | 0 | Cold Shutdown | Event Text DEGRADED CONDITION - SMALL LEAK ON RHR INJECTION DRAIN LINE
"After shutting down for refueling outage, a small leak was discovered on a 1-inch drain line for the 'A' Loop RHR injection line. This leak is at a weld.
"Tech Spec 3.4.4 was entered for RCS Operational Leakage due to potential Class I pressure boundary leakage.
"This report is being made IAW 10CFR50.72(b)(3)."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 42004 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: ARLON COSTA | Notification Date: 09/21/2005
Notification Time: 02:37 [ET]
Event Date: 09/20/2005
Event Time: 22:40 [CDT]
Last Update Date: 09/21/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
MICHAEL SHANNON (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 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN COMMENCED DUE TO INOPERABILITY OF RESIDUAL HEAT REMOVAL CONTAINMENT SUMP ISOLATION VALVES
"At 2240 09/20/2005 an engineering evaluation concluded that the Residual Heat Removal Containment Sump Isolation Valves were inoperable based on their inability to open against a higher differential pressure than had been previously evaluated. Historically Wolf Creek has operated with the Component Cooling Water isolated to the Residual Heat Removal Heat Exchangers. If the pumps started during accident conditions there is a potential that the pump heat generated could cause system pressure to increase to the suction relief valve setting of 450 psig. Testing of the valves has shown that they are capable of opening with 207 psid across the valve.
"Technical Specification 3.0.3 was entered at 2240 9/20/2005 due to the inoperability of both Residual Heat Removal trains. Power reduction was commenced at 2340. Component Cooling Water was aligned to the Residual Heat Removal Heat Exchangers at 0004 9/21/2005 restoring operability of the Residual Heat Removal trains. At 0017 9/21/2005 actions were commenced to restore power to 100%.
"This event is reportable under 10 CFR50.72(b)(2)(i) Technical Specification required shut down (4 hour) and 10 CFR50.72(b)(3)(v)(B) Event or Condition that could have prevented fulfillment of a Safety Function (8 hour).
"The NRC Resident has been contacted." | |