Event Notification Report for September 26, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/25/2011 - 09/26/2011
EVENT NUMBERS
4732247292472934729447298
Power Reactor
Event Number: 47322
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: OTTO GUSTAFSON
HQ OPS Officer: JOE O'HARA
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: OTTO GUSTAFSON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/05/2011
Notification Time: 18:00 [ET]
Event Date: 09/26/2011
Event Time: 06:02 [EDT]
Last Update Date: 10/05/2011
Notification Time: 18:00 [ET]
Event Date: 09/26/2011
Event Time: 06:02 [EDT]
Last Update Date: 10/05/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
MONTE PHILLIPS (R3DO)
MONTE PHILLIPS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
UNANALYZED CONDITION - APPENDIX R EQUIPMENT MAY NOT HAVE BEEN AVAILABLE
"An Appendix R non-compliance issue was identified. When the plant automatically tripped on September 25, 2011, an unexpected automatic trip was identified in DC shunt trip breakers 72-01 and 72-02. This automatic trip function was not considered in the Appendix R electrical coordination evaluation. Preliminary analysis has shown that if the shunt trip breaker would have automatically opened due to fire induced fault currents, then Appendix R credited equipment may have been lost unexpectedly. The operability evaluation performed, resulted in increasing the shunt trip settings to maximum, and implementing compensatory measures to isolate some non-safety related electrical loads, which restored compliance with 10 CFR 50 Appendix R.
"The licensee notified the NRC Senior Resident Inspector."
CR# PLP2011-04835
"An Appendix R non-compliance issue was identified. When the plant automatically tripped on September 25, 2011, an unexpected automatic trip was identified in DC shunt trip breakers 72-01 and 72-02. This automatic trip function was not considered in the Appendix R electrical coordination evaluation. Preliminary analysis has shown that if the shunt trip breaker would have automatically opened due to fire induced fault currents, then Appendix R credited equipment may have been lost unexpectedly. The operability evaluation performed, resulted in increasing the shunt trip settings to maximum, and implementing compensatory measures to isolate some non-safety related electrical loads, which restored compliance with 10 CFR 50 Appendix R.
"The licensee notified the NRC Senior Resident Inspector."
CR# PLP2011-04835
Power Reactor
Event Number: 47292
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES MORGAN
HQ OPS Officer: JOHN KNOKE
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES MORGAN
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/26/2011
Notification Time: 14:27 [ET]
Event Date: 09/26/2011
Event Time: 14:00 [EDT]
Last Update Date: 09/26/2011
Notification Time: 14:27 [ET]
Event Date: 09/26/2011
Event Time: 14:00 [EDT]
Last Update Date: 09/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
LAWRENCE DOERFLEIN (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 93 | Power Operation | 93 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
800 MHZ RADIO SYSTEM TEMPORARILY REMOVED FROM SERVICE DUE TO DEGRADED ANTENNA
"The site's 800 MHz radio system was removed from service for approximately one (1) hour to support pre-planned maintenance to repair a degraded antenna. While the 800 MHz radio system is out of service, it will not be possible to activate any of the site's emergency sirens from any of the risk county Emergency Operations Centers nor from the plant. For the period of time that the sirens are non-functional, the three risk counties will be prepared to utilize the back-up method of route alerting to alert residents."
The licensee has notified the NRC Resident Inspector.
"The site's 800 MHz radio system was removed from service for approximately one (1) hour to support pre-planned maintenance to repair a degraded antenna. While the 800 MHz radio system is out of service, it will not be possible to activate any of the site's emergency sirens from any of the risk county Emergency Operations Centers nor from the plant. For the period of time that the sirens are non-functional, the three risk counties will be prepared to utilize the back-up method of route alerting to alert residents."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 47293
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: RICHARD ROGALSKI
HQ OPS Officer: JOHN KNOKE
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: RICHARD ROGALSKI
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/26/2011
Notification Time: 14:48 [ET]
Event Date: 09/26/2011
Event Time: 11:45 [EDT]
Last Update Date: 09/26/2011
Notification Time: 14:48 [ET]
Event Date: 09/26/2011
Event Time: 11:45 [EDT]
Last Update Date: 09/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MARK LESSER (R2DO)
MARK LESSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO ONE LOOP LOW FLOW SIGNAL
"At 1145 hours EDT on September 26, 2011, with the unit in Mode 1 at 100% power, an automatic reactor trip occurred. The reactor trip signal was based on the One Loop Low Flow reactor protection function. All Reactor Coolant Pumps (RCP) remained running.
"The Auxiliary Feedwater System automatically actuated, as expected due to low steam generator water level, and provided feedwater to the steam generators. The steam generator and pressurizer Power Operated Relief Valves (PORVs) and the Main Steam Safety Valves did not open during the event. All control rods indicated fully inserted following the reactor trip.
"The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable. Decay heat is being removed via the condenser. The reactor is currently stable in Mode 3.
"The cause of the reactor trip is under investigation."
"At 1145 hours EDT on September 26, 2011, with the unit in Mode 1 at 100% power, an automatic reactor trip occurred. The reactor trip signal was based on the One Loop Low Flow reactor protection function. All Reactor Coolant Pumps (RCP) remained running.
"The Auxiliary Feedwater System automatically actuated, as expected due to low steam generator water level, and provided feedwater to the steam generators. The steam generator and pressurizer Power Operated Relief Valves (PORVs) and the Main Steam Safety Valves did not open during the event. All control rods indicated fully inserted following the reactor trip.
"The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable. Decay heat is being removed via the condenser. The reactor is currently stable in Mode 3.
"The cause of the reactor trip is under investigation."
Power Reactor
Event Number: 47294
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: DOUG GORSE
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: DOUG GORSE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/26/2011
Notification Time: 15:09 [ET]
Event Date: 09/26/2011
Event Time: 15:00 [EDT]
Last Update Date: 09/26/2011
Notification Time: 15:09 [ET]
Event Date: 09/26/2011
Event Time: 15:00 [EDT]
Last Update Date: 09/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
LAWRENCE DOERFLEIN (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
NEW RIVER HYDRAULIC ANALYSIS RAISES MAXIMUM FLOOD LEVEL
"TMI new river analysis indicates level above existing UFSAR [Updated Final Safety Analysis Report] flood analysis. At about 15:00 [EDT] on September 26, 2011, a revised River Stage Discharge Analysis was completed and concluded that the Probable Maximum Flood (PMF) water level is higher than previously described in the safety analysis report. This unanalyzed condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B).
"Actions to protect the plant for the higher PMF river level have been implemented. The flood barrier gates that protect safety related equipment have been modified to accommodate the revised river levels. No onsite flood water levels have occurred that could potentially challenge the existing flood barrier system.
"The licensee notified the NRC Resident Inspector."
The licensee will be making a courtesy media notification.
"TMI new river analysis indicates level above existing UFSAR [Updated Final Safety Analysis Report] flood analysis. At about 15:00 [EDT] on September 26, 2011, a revised River Stage Discharge Analysis was completed and concluded that the Probable Maximum Flood (PMF) water level is higher than previously described in the safety analysis report. This unanalyzed condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B).
"Actions to protect the plant for the higher PMF river level have been implemented. The flood barrier gates that protect safety related equipment have been modified to accommodate the revised river levels. No onsite flood water levels have occurred that could potentially challenge the existing flood barrier system.
"The licensee notified the NRC Resident Inspector."
The licensee will be making a courtesy media notification.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Agreement State
Event Number: 47298
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: BASF CORPORATION
Region: 4
City: FREEPORT State: TX
County:
License #: 01021
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: BILL HUFFMAN
Licensee: BASF CORPORATION
Region: 4
City: FREEPORT State: TX
County:
License #: 01021
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/27/2011
Notification Time: 10:06 [ET]
Event Date: 09/26/2011
Event Time: 00:00 [CDT]
Last Update Date: 11/17/2011
Notification Time: 10:06 [ET]
Event Date: 09/26/2011
Event Time: 00:00 [CDT]
Last Update Date: 11/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GREG WERNER (R4DO)
ANGELA MCINTOSH (FSME)
GREG WERNER (R4DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - STUCK SHUTTER ON FIXED PROCESS GAUGE
The following information was received from the Texas Department of State Health Services via e-mail:
"On September 26, 2011, the licensee reported that while preparing to enter a vessel, the shutter on a Ronan model SA-1 nuclear gauge containing 2000 millicuries of Cesium (Cs) -137 failed to shut and is stuck in the normally open position. The source serial number is 2943GK. No significant exposure has occurred due to this event. The gauge is located at a height of 150 feet on the tank. The licensee contacted a technical representative and expects to repair or replace the gauge at the end of the week. The cause for the event is under investigation. Additional information will be provided as it is received IAW SA 300."
* * * RETRACTION FROM ART TUCKER TO JOHN KNOKE AT 1016 EST ON 11/17/11 * * *
The following information was received from the Texas Department of State Health Services via e-mail:
"The manufacturer inspected the gauge at the licensee's location and determined that the gauge was functioning properly. They also determined that the radiation measurements taken by the licensee to determine if the shutter was closed where taken at a distance that was closer than the reference reading causing the elevated readings. There was no reportable event."
Notified the R4DO (Blair Spitzberg) and FSME (Angela McIntosh)
Texas Incident #: I-8887
The following information was received from the Texas Department of State Health Services via e-mail:
"On September 26, 2011, the licensee reported that while preparing to enter a vessel, the shutter on a Ronan model SA-1 nuclear gauge containing 2000 millicuries of Cesium (Cs) -137 failed to shut and is stuck in the normally open position. The source serial number is 2943GK. No significant exposure has occurred due to this event. The gauge is located at a height of 150 feet on the tank. The licensee contacted a technical representative and expects to repair or replace the gauge at the end of the week. The cause for the event is under investigation. Additional information will be provided as it is received IAW SA 300."
* * * RETRACTION FROM ART TUCKER TO JOHN KNOKE AT 1016 EST ON 11/17/11 * * *
The following information was received from the Texas Department of State Health Services via e-mail:
"The manufacturer inspected the gauge at the licensee's location and determined that the gauge was functioning properly. They also determined that the radiation measurements taken by the licensee to determine if the shutter was closed where taken at a distance that was closer than the reference reading causing the elevated readings. There was no reportable event."
Notified the R4DO (Blair Spitzberg) and FSME (Angela McIntosh)
Texas Incident #: I-8887