Event Notification Report for March 01, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/29/2012 - 03/01/2012
EVENT NUMBERS
47712477134771047723
Fuel Cycle Facility
Event Number: 47712
Facility: B&W NUCLEAR OPERATING GROUP, INC.
Region: 2 State: VA
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: KENNY KIRBY
HQ OPS Officer: STEVE SANDIN
Region: 2 State: VA
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: KENNY KIRBY
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/01/2012
Notification Time: 12:12 [ET]
Event Date: 03/01/2012
Event Time: 09:15 [EST]
Last Update Date: 03/01/2012
Notification Time: 12:12 [ET]
Event Date: 03/01/2012
Event Time: 09:15 [EST]
Last Update Date: 03/01/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
Person (Organization):
MARK FRANKE (R2DO)
JAMES RUBENSTONE (NMSS)
FUEL GROUP via email
MARK FRANKE (R2DO)
JAMES RUBENSTONE (NMSS)
FUEL GROUP via email
EXTERNAL RADIATION LEVELS EXCEEDED PART 20 LIMITS DURING SHIPMENT
"Evaluation of LTC [Lynchburg Technology Center] AmBe Shipment issues for 03/01/12 receipt.
"The conditions for reporting under the requirements of 10 CFR 20 1906(d) have been met. QWI 14.1.10 Classification & Notification Criteria for Unusual Incidents Radiation Protection section - for shipments, bases reporting requirements on receipt of a shipment with radiation or contamination levels in excess of 10 CFR 20.1906(d). This requirement was exceeded and an NRC report is required. The truck cab sleeping area (normally occupied space) dose rate of 3.4 mRem/hr is greater than the allowable limit of 2.0 mRem/hr. The private carrier personnel state that they do not have dosimetry.
"Immediate Actions Taken: Digital photographs have been taken, confirmatory surveys (with other instruments) were taken, additional spot surveys were taken, the shipper has been notified, and an evaluation of the regulations has been made."
The licensee informed the NRC Resident Inspector.
"Evaluation of LTC [Lynchburg Technology Center] AmBe Shipment issues for 03/01/12 receipt.
"The conditions for reporting under the requirements of 10 CFR 20 1906(d) have been met. QWI 14.1.10 Classification & Notification Criteria for Unusual Incidents Radiation Protection section - for shipments, bases reporting requirements on receipt of a shipment with radiation or contamination levels in excess of 10 CFR 20.1906(d). This requirement was exceeded and an NRC report is required. The truck cab sleeping area (normally occupied space) dose rate of 3.4 mRem/hr is greater than the allowable limit of 2.0 mRem/hr. The private carrier personnel state that they do not have dosimetry.
"Immediate Actions Taken: Digital photographs have been taken, confirmatory surveys (with other instruments) were taken, additional spot surveys were taken, the shipper has been notified, and an evaluation of the regulations has been made."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 47713
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RAUL MARTINEZ
HQ OPS Officer: JOHN KNOKE
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RAUL MARTINEZ
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/01/2012
Notification Time: 18:41 [ET]
Event Date: 03/01/2012
Event Time: 17:05 [CST]
Last Update Date: 03/01/2012
Notification Time: 18:41 [ET]
Event Date: 03/01/2012
Event Time: 17:05 [CST]
Last Update Date: 03/01/2012
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):
RYAN LANTZ (R4DO)
RYAN LANTZ (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
BATTERY ROOM VENTILATION SYSTEM DEGRADED
"While Units 1 and 2 were in Mode 1, operating at 100% power, an issue was identified with the doors for the safety related battery rooms and their normal position. Several doors to the battery rooms were found to be held open via electromagnetic door devices. These doors are an integral part of their battery room exhaust system. As designed, there is no uninterruptible power to the door mechanisms, all the doors are expected to close in the event of a Loss of Offsite Power.
"The closure of the doors to the battery rooms, being an integral part of the exhaust system, would disrupt ventilation in the battery rooms and could allow hydrogen to increase to unacceptable levels during Loss of Offsite Power events.
"Compensatory measures have been taken to secure the doors open to maintain the hydrogen purging function before required limits are reached. The battery room ventilation system remains functional supporting operability of the batteries.
"Luminant Power determined this issue to be reportable as an unanalyzed condition per 10 CFR 50.72(b)(3)(ii)(B)."
The licensee will notify the NRC Resident Inspector.
"While Units 1 and 2 were in Mode 1, operating at 100% power, an issue was identified with the doors for the safety related battery rooms and their normal position. Several doors to the battery rooms were found to be held open via electromagnetic door devices. These doors are an integral part of their battery room exhaust system. As designed, there is no uninterruptible power to the door mechanisms, all the doors are expected to close in the event of a Loss of Offsite Power.
"The closure of the doors to the battery rooms, being an integral part of the exhaust system, would disrupt ventilation in the battery rooms and could allow hydrogen to increase to unacceptable levels during Loss of Offsite Power events.
"Compensatory measures have been taken to secure the doors open to maintain the hydrogen purging function before required limits are reached. The battery room ventilation system remains functional supporting operability of the batteries.
"Luminant Power determined this issue to be reportable as an unanalyzed condition per 10 CFR 50.72(b)(3)(ii)(B)."
The licensee will notify the NRC Resident Inspector.
Power Reactor
Event Number: 47710
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: PETE SNYDER
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: PETE SNYDER
Notification Date: 03/01/2012
Notification Time: 05:51 [ET]
Event Date: 03/01/2012
Event Time: 00:00 [EST]
Last Update Date: 03/01/2012
Notification Time: 05:51 [ET]
Event Date: 03/01/2012
Event Time: 00:00 [EST]
Last Update Date: 03/01/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR PROTECTION SYSTEM ACTUATION DUE TO AUTOMATIC TURBINE RUNBACK
"On March 1,2012, at approximately 0224 [EST], a manual Reactor Protection System (RPS) actuation was initiated due to 3 turbine bypass valves going open as a result of an automatic turbine runback signal. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig.
"No Emergency Core Cooling Systems were required or utilized to respond to the event and there were no other reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed. The cause of the automatic turbine runback has not been determined and is being investigated.
"During the transient, Reactor Water Cleanup System (RWCU) tripped. No automatic isolation signal was received.
"At the time of the event, restoration of a Stator Water Cooling pressure gauge was being performed [following maintenance].
"The NRC Resident Inspector has been notified."
"On March 1,2012, at approximately 0224 [EST], a manual Reactor Protection System (RPS) actuation was initiated due to 3 turbine bypass valves going open as a result of an automatic turbine runback signal. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig.
"No Emergency Core Cooling Systems were required or utilized to respond to the event and there were no other reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed. The cause of the automatic turbine runback has not been determined and is being investigated.
"During the transient, Reactor Water Cleanup System (RWCU) tripped. No automatic isolation signal was received.
"At the time of the event, restoration of a Stator Water Cooling pressure gauge was being performed [following maintenance].
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 47723
Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: HOWARD MAHAN
HQ OPS Officer: VINCE KLCO
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: HOWARD MAHAN
HQ OPS Officer: VINCE KLCO
Notification Date: 03/07/2012
Notification Time: 16:00 [ET]
Event Date: 03/01/2012
Event Time: 19:06 [EST]
Last Update Date: 03/07/2012
Notification Time: 16:00 [ET]
Event Date: 03/01/2012
Event Time: 19:06 [EST]
Last Update Date: 03/07/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
GEORGE HOPPER (R2DO)
GEORGE HOPPER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Under Construction | 0 | Under Construction |
| 4 | N | N | 0 | Under Construction | 0 | Under Construction |
FAILURE TO FOLLOW SITE FITNESS FOR DUTY PROCEDURES
"On March 01, 2012, it was discovered that a [Contractor] program manager intentionally failed to implement a procedure change as instructed by management. An initial investigation has determined that interim compensatory actions were in place prior to this pending procedural change. The involved manager's access authorization has been revoked. Southern Nuclear Operating Company, Inc. (SNC) was notified by [the Contractor] of this discovery on March 06, 2012 at 19:00 EST.
"SNC is providing this notification under the provisions of 10 CFR 26.719(b)(3) as an intentional act that casts doubt on the integrity of the FFD program.
"At the time of this report, no regulatory barriers for individuals assigned to perform duties that require them to be subject to the FFD program have been breached regarding this event."
The licensee notified the NRC Resident Inspector.
"On March 01, 2012, it was discovered that a [Contractor] program manager intentionally failed to implement a procedure change as instructed by management. An initial investigation has determined that interim compensatory actions were in place prior to this pending procedural change. The involved manager's access authorization has been revoked. Southern Nuclear Operating Company, Inc. (SNC) was notified by [the Contractor] of this discovery on March 06, 2012 at 19:00 EST.
"SNC is providing this notification under the provisions of 10 CFR 26.719(b)(3) as an intentional act that casts doubt on the integrity of the FFD program.
"At the time of this report, no regulatory barriers for individuals assigned to perform duties that require them to be subject to the FFD program have been breached regarding this event."
The licensee notified the NRC Resident Inspector.