Event Notification Report for November 09, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/08/2008 - 11/09/2008
Power Reactor
Event Number: 44647
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CURTIS DUNMORE
HQ OPS Officer: VINCE KLCO
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CURTIS DUNMORE
HQ OPS Officer: VINCE KLCO
Notification Date: 11/09/2008
Notification Time: 12:08 [ET]
Event Date: 11/09/2008
Event Time: 11:08 [EST]
Last Update Date: 11/09/2008
Notification Time: 12:08 [ET]
Event Date: 11/09/2008
Event Time: 11:08 [EST]
Last Update Date: 11/09/2008
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):
MALCOLM WIDMANN (R2)
MALCOLM WIDMANN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO SPURIOUS SRV OPENING
"One hour reportable event based on a safety relief valve (SRV) failure to close (NUREG 0626 and NUREG 0660).
"On 11/09/08 at approximately 11:08 with Unit 2 at 100% steady state power SRV 2-B21-F013H spuriously failed full open with no operator action or testing in progress. The valve's control switch was cycled as required by Abnormal Operating Procedure AOP-30 with no success. At 1113 the valve was successfully closed by pulling the associated fuses. At 1117, a manual reactor scram was inserted based on a Torus temperature of 109.8 degrees F (Technical Specifications require a scram to be inserted at 110 degrees F). All control rods [fully] inserted from the manual scram signal. Reactor water level lowered to Low Level 2 resulting in Primary Containment Isolation System (PCIS) isolations of Groups 2, 3, 6, and 8. In addition, this resulted in a Reactor Core Isolation Cooling (RCIC) system actuation and injection into the reactor. The High Pressure Coolant Injection (HPCI) system actuated but did not inject because reactor water level recovered. An Alternate Rod Insertion signal was received, the Standby Gas Treatment (SBGT) system initiated, and the Reactor Recirculation Pumps tripped as designed.
"Plant safety systems responded as designed to the transient.
"[Licensee] investigations are underway to determine the cause of the SRV failure."
Reactor decay heat is being removed through the main turbine bypass valves to the condenser. Reactor make-up is being maintained by the normal feedwater system. The plant is in its normal shutdown electrical lineup supplied by offsite power. The diesel generators are available for service to the plant.
The Licensee notified the NRC Resident Inspector.
"One hour reportable event based on a safety relief valve (SRV) failure to close (NUREG 0626 and NUREG 0660).
"On 11/09/08 at approximately 11:08 with Unit 2 at 100% steady state power SRV 2-B21-F013H spuriously failed full open with no operator action or testing in progress. The valve's control switch was cycled as required by Abnormal Operating Procedure AOP-30 with no success. At 1113 the valve was successfully closed by pulling the associated fuses. At 1117, a manual reactor scram was inserted based on a Torus temperature of 109.8 degrees F (Technical Specifications require a scram to be inserted at 110 degrees F). All control rods [fully] inserted from the manual scram signal. Reactor water level lowered to Low Level 2 resulting in Primary Containment Isolation System (PCIS) isolations of Groups 2, 3, 6, and 8. In addition, this resulted in a Reactor Core Isolation Cooling (RCIC) system actuation and injection into the reactor. The High Pressure Coolant Injection (HPCI) system actuated but did not inject because reactor water level recovered. An Alternate Rod Insertion signal was received, the Standby Gas Treatment (SBGT) system initiated, and the Reactor Recirculation Pumps tripped as designed.
"Plant safety systems responded as designed to the transient.
"[Licensee] investigations are underway to determine the cause of the SRV failure."
Reactor decay heat is being removed through the main turbine bypass valves to the condenser. Reactor make-up is being maintained by the normal feedwater system. The plant is in its normal shutdown electrical lineup supplied by offsite power. The diesel generators are available for service to the plant.
The Licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 44648
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE HENRY
HQ OPS Officer: VINCE KLCO
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE HENRY
HQ OPS Officer: VINCE KLCO
Notification Date: 11/09/2008
Notification Time: 20:44 [ET]
Event Date: 11/09/2008
Event Time: 15:30 [EST]
Last Update Date: 11/11/2008
Notification Time: 20:44 [ET]
Event Date: 11/09/2008
Event Time: 15:30 [EST]
Last Update Date: 11/11/2008
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):
MALCOLM WIDMANN (R2)
MALCOLM WIDMANN (R2)
| 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 |
TECHNICAL SUPPORT CENTER HVAC OUT OF SERVICE
"The TSC Normal HVAC (A-1563-A7-001) and Normal Chilled Water Pump (A-1564-P7-001) tripped for unknown reasons after approximately 10 minutes of operation following restoration to normal from surveillance 14400A-1.
"This report is being made per Technical Requirements Manual 13.13.1, action B.2. With the TSC Normal HVAC and Chilled Water Pump inoperable, the Functionality of the TSC has been lost due to inability to maintain proper climate control. The alternate TSC facility is available and actions are being taken to return the TSC to Functional status with a high priority. The NRC Resident Inspector has been notified."
* * * UPDATE ON 11/11/2008 AT 1534 FROM STEPHEN HARRIS TO MARK ABRAMOVITZ * * *
The TSC Emergency Response Facility was restored to Operable status on 11/11/2008 at 1442.
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Bonser).
"The TSC Normal HVAC (A-1563-A7-001) and Normal Chilled Water Pump (A-1564-P7-001) tripped for unknown reasons after approximately 10 minutes of operation following restoration to normal from surveillance 14400A-1.
"This report is being made per Technical Requirements Manual 13.13.1, action B.2. With the TSC Normal HVAC and Chilled Water Pump inoperable, the Functionality of the TSC has been lost due to inability to maintain proper climate control. The alternate TSC facility is available and actions are being taken to return the TSC to Functional status with a high priority. The NRC Resident Inspector has been notified."
* * * UPDATE ON 11/11/2008 AT 1534 FROM STEPHEN HARRIS TO MARK ABRAMOVITZ * * *
The TSC Emergency Response Facility was restored to Operable status on 11/11/2008 at 1442.
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Bonser).
Power Reactor
Event Number: 44649
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JULIOUS WHITWORTH
HQ OPS Officer: VINCE KLCO
Region: 2 State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JULIOUS WHITWORTH
HQ OPS Officer: VINCE KLCO
Notification Date: 11/09/2008
Notification Time: 23:29 [ET]
Event Date: 11/09/2008
Event Time: 18:21 [EST]
Last Update Date: 11/09/2008
Notification Time: 23:29 [ET]
Event Date: 11/09/2008
Event Time: 18:21 [EST]
Last Update Date: 11/09/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MALCOLM WIDMANN (R2)
MALCOLM WIDMANN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | N | 0 | Hot Standby | 0 | Hot Standby |
REACTOR TRIP BREAKERS OPENED MANUALLY DUE TO INDICATED DROPPED CONTROL ROD
"On 11/19/08 at 1821 with unit 2 in Mode 3, the unit 2 reactor trip breakers were opened from the Main Control Room (MCR) due to indications of a Shutdown Bank "A" Rod E-11 dropping into the Reactor Core. At the time the reactor trip breakers were opened, the MCR Operators were in the process of withdrawing Shutdown Banks in preparations for entry into Mode 2. All other Shutdown Banks and Control Banks were inserted at the time the reactor trip breakers were opened. In addition, a Feedwater Isolation Signal was generated as designed. All safety related equipment operated as designed.
"The Plant is being maintained in Mode 3 at NOT/NOP, approximately 547 F and 2235 psig, with AFW supplying the S/G's and Steam Dumps to Main Condenser removing decay heat.
"No primary system or steam generator safety valves opened due to this trip.
"An investigation has been initiated to determine the cause of the indications of Shutdown Bank 'A' Rod E-11 dropping into the Reactor Core."
The licensee notified the NRC Resident Inspector.
"On 11/19/08 at 1821 with unit 2 in Mode 3, the unit 2 reactor trip breakers were opened from the Main Control Room (MCR) due to indications of a Shutdown Bank "A" Rod E-11 dropping into the Reactor Core. At the time the reactor trip breakers were opened, the MCR Operators were in the process of withdrawing Shutdown Banks in preparations for entry into Mode 2. All other Shutdown Banks and Control Banks were inserted at the time the reactor trip breakers were opened. In addition, a Feedwater Isolation Signal was generated as designed. All safety related equipment operated as designed.
"The Plant is being maintained in Mode 3 at NOT/NOP, approximately 547 F and 2235 psig, with AFW supplying the S/G's and Steam Dumps to Main Condenser removing decay heat.
"No primary system or steam generator safety valves opened due to this trip.
"An investigation has been initiated to determine the cause of the indications of Shutdown Bank 'A' Rod E-11 dropping into the Reactor Core."
The licensee notified the NRC Resident Inspector.