Event Notification Report for June 16, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/15/2005 - 06/16/2005
Power Reactor
Event Number: 41780
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: JEFF ROTTON
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: JEFF ROTTON
Notification Date: 06/16/2005
Notification Time: 13:44 [ET]
Event Date: 06/16/2005
Event Time: 09:23 [EDT]
Last Update Date: 06/16/2005
Notification Time: 13:44 [ET]
Event Date: 06/16/2005
Event Time: 09:23 [EDT]
Last Update Date: 06/16/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
THOMAS KOZAK (R3)
THOMAS KOZAK (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
BOTH RHR LPCI DIVISIONS INOPERABLE DUE TO VALVE FAILURE
"On June 16, 2005 at 0923 EDT, with the plant in Mode 1 at 100% reactor power, both divisions of Residual Heat Removal (RHR) were declared inoperable for the Low Pressure Coolant Injection (LPCI) mode of operation due to a failure of E1150-F017B, Division 2 LPCI Outboard Injection Valve. While performing the Division 2 RHR Pump & Valve Operability Surveillance following a planned Division 2 RHR system outage, E1150-F017B closed properly but failed to open during its required stroke time test. With this valve closed and unable to automatically open, LPCI injection into the RPV from both divisions of RHR would be prevented if LPCI Loop Select Logic selected the Division 2 loop for injection. Therefore, this failure rendered both divisions of RHR inoperable for the LPCI function. LCO 3.5.1.J was entered, which requires immediate entry into LCO 3.0.3. The cause of the failure was subsequently identified and E1150-F017B was returned to its normally open position. At 1146 EDT, Division 1 RHR was declared operable for the LPCI function, and LCO 3.5.1.J and LCO 3.0.3 were exited. The plant remained at 100% power throughout the event.
"The NRC resident inspector has been notified. This report is being made pursuant to 10CFR 50.72(b)(3)(v)(D)."
"On June 16, 2005 at 0923 EDT, with the plant in Mode 1 at 100% reactor power, both divisions of Residual Heat Removal (RHR) were declared inoperable for the Low Pressure Coolant Injection (LPCI) mode of operation due to a failure of E1150-F017B, Division 2 LPCI Outboard Injection Valve. While performing the Division 2 RHR Pump & Valve Operability Surveillance following a planned Division 2 RHR system outage, E1150-F017B closed properly but failed to open during its required stroke time test. With this valve closed and unable to automatically open, LPCI injection into the RPV from both divisions of RHR would be prevented if LPCI Loop Select Logic selected the Division 2 loop for injection. Therefore, this failure rendered both divisions of RHR inoperable for the LPCI function. LCO 3.5.1.J was entered, which requires immediate entry into LCO 3.0.3. The cause of the failure was subsequently identified and E1150-F017B was returned to its normally open position. At 1146 EDT, Division 1 RHR was declared operable for the LPCI function, and LCO 3.5.1.J and LCO 3.0.3 were exited. The plant remained at 100% power throughout the event.
"The NRC resident inspector has been notified. This report is being made pursuant to 10CFR 50.72(b)(3)(v)(D)."
Power Reactor
Event Number: 41781
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: STEVE SANDIN
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/16/2005
Notification Time: 22:16 [ET]
Event Date: 06/16/2005
Event Time: 19:02 [CDT]
Last Update Date: 06/16/2005
Notification Time: 22:16 [ET]
Event Date: 06/16/2005
Event Time: 19:02 [CDT]
Last Update Date: 06/16/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JACK WHITTEN (R4)
JACK WHITTEN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 67 | Power Operation |
UNIT COMMENCED A TECH SPEC REQUIRED SHUTDOWN DUE TO AN ELECTRICAL PROBLEM AFFECTING A SAFETY RELATED BATTERY
"At 1302 [CDT], 6/16/05, during investigation of an electrical ground affecting safety related battery NK04, a channel failure alarm actuated for SA075B, Main Steam and Feedwater Isolation Actuation control panel. Work at KJ122, 'B' Emergency Diesel Generator [EDG] local control panel, was suspended and troubleshooting efforts commenced to determine the cause of the SA075B alarm. Concurrently, SA075B was declared Inoperable at 1302 [CDT] and Engineered Safety Feature Actuation System Technical Specification Action statement 3.3.2.S was entered which allowed 6 hours to restore the train to Operable status, or be in Mode 3 within the following 6 hours. As of 1902 [CDT], all repairs and retests had not been completed. A reactor shutdown was commenced at 1902 [CDT] in accordance with Technical Specification 3.3.2.S, which is reportable per 10CFR50.72(b)(2)(i)."
The licensee is continuing their investigation to identify cause of the electrical ground but does not anticipate exiting the LCO Action Statement before completing the Unit shutdown. Safety related battery NK04 is currently operable with the faulted loads isolated. The "B" EDG remains Inoperable at this time for troubleshooting.
The licensee informed the NRC Resident Inspector.
"At 1302 [CDT], 6/16/05, during investigation of an electrical ground affecting safety related battery NK04, a channel failure alarm actuated for SA075B, Main Steam and Feedwater Isolation Actuation control panel. Work at KJ122, 'B' Emergency Diesel Generator [EDG] local control panel, was suspended and troubleshooting efforts commenced to determine the cause of the SA075B alarm. Concurrently, SA075B was declared Inoperable at 1302 [CDT] and Engineered Safety Feature Actuation System Technical Specification Action statement 3.3.2.S was entered which allowed 6 hours to restore the train to Operable status, or be in Mode 3 within the following 6 hours. As of 1902 [CDT], all repairs and retests had not been completed. A reactor shutdown was commenced at 1902 [CDT] in accordance with Technical Specification 3.3.2.S, which is reportable per 10CFR50.72(b)(2)(i)."
The licensee is continuing their investigation to identify cause of the electrical ground but does not anticipate exiting the LCO Action Statement before completing the Unit shutdown. Safety related battery NK04 is currently operable with the faulted loads isolated. The "B" EDG remains Inoperable at this time for troubleshooting.
The licensee informed the NRC Resident Inspector.
Other Nuclear Material
Event Number: 41834
Rep Org: MEDTRONIC
Licensee: MEDTRONIC
Region: 3
City: FRIDLEY State: MN
County:
License #:
Agreement: N
Docket:
NRC Notified By: SCOTT MORRISON
HQ OPS Officer: JOHN MacKINNON
Licensee: MEDTRONIC
Region: 3
City: FRIDLEY State: MN
County:
License #:
Agreement: N
Docket:
NRC Notified By: SCOTT MORRISON
HQ OPS Officer: JOHN MacKINNON
Notification Date: 07/11/2005
Notification Time: 15:14 [ET]
Event Date: 06/16/2005
Event Time: 12:00 [CDT]
Last Update Date: 07/11/2005
Notification Time: 15:14 [ET]
Event Date: 06/16/2005
Event Time: 12:00 [CDT]
Last Update Date: 07/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
PATTY PELKE (R3)
MICHELE BURGESS (NMSS)
TAS(e-mail) (NSIR)
CANADA (FAXED)
PATTY PELKE (R3)
MICHELE BURGESS (NMSS)
TAS(e-mail) (NSIR)
CANADA (FAXED)
STOLEN AIR IONIZER CONTAINING A GENERAL LICENSED POLONIUM-210 SOURCE
Between June 16th and the 22nd a 10 millicurie Po-210 air ionizer was stolen from their facility. Medtronic alerted their security and filed a Police report on the stolen Po-210 air ionizer. The Model number of the air ionizer is P2021-8000 and the serial number is A2EM605. On June 15, 2005 Medtronic received the air ionizer from NRD located in Grand Island, NY (The air ionizer is leased through NRD). Medtronic stated that all future devices will be stored in a locked cabinet.
Between June 16th and the 22nd a 10 millicurie Po-210 air ionizer was stolen from their facility. Medtronic alerted their security and filed a Police report on the stolen Po-210 air ionizer. The Model number of the air ionizer is P2021-8000 and the serial number is A2EM605. On June 15, 2005 Medtronic received the air ionizer from NRD located in Grand Island, NY (The air ionizer is leased through NRD). Medtronic stated that all future devices will be stored in a locked cabinet.