Event Notification Report for August 15, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/14/2010 - 08/15/2010
Power Reactor
Event Number: 46175
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN LEWIS
HQ OPS Officer: DONG HWA PARK
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN LEWIS
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/15/2010
Notification Time: 04:15 [ET]
Event Date: 08/15/2010
Event Time: 00:45 [CDT]
Last Update Date: 08/15/2010
Notification Time: 04:15 [ET]
Event Date: 08/15/2010
Event Time: 00:45 [CDT]
Last Update Date: 08/15/2010
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):
STEVEN RUDISAIL (R2DO)
STEVEN RUDISAIL (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 96 | Power Operation |
TS REQUIRED SHUTDOWN ENTERED DUE TO HIGH CONTAINMENT TEMPERATURE
"Due to failure of Service Water from RCP Motor Air Cooler valve MOV3134 to stroke satisfactorily during scheduled surveillance testing, [the licensee] entered TS 3.6.3 Condition A for Containment Isolation Valves. MOV3134 did not indicate full closed by remote indication in the Control Room when time-stroked at 0119, 8/14/10. Consequently, the isolation valve inside containment, MOV3131, was closed and deenergized to provide containment isolation. This isolated a source of Service Water cooling for containment, and the average temperature of containment started trending up from 117.5F at 0000, 8/14/10. At 1400, 8/14/10, containment average temperature exceeded 120F and entry into TS 3.6.5 Condition A was required. At 2200, 8/14/10, containment average temperature had not been restored to [less than or equal to] 120F, and TS 3.6.5 Condition B was entered. To ensure compliance with TS 3.6.5 Condition B, a ramp down to MODE 3 was initiated at 0045, 8/15/10.
"At 0057, 8/15/10, the NRC authorized enforcement discretion for Farley Nuclear Plant Unit 1 with regard to LCO 3.6.5 and containment temperature in excess of 120F. The ramp down was halted and power stabilized at 96% Rx power. The enforcement discretion duration is 18 hours starting from 2200, 8/14/10. There were two stipulations on the discretion:
"1. If the LLRT [Local Leak Rate Test] on MOV3134 fails, a controlled shutdown will be initiated. Time from the enforcement discretion will be used as necessary to achieve a controlled shutdown.
"2. If containment average temperature exceeds 122F, a controlled shutdown will be initiated. Time from the enforcement discretion will be used as necessary to achieve a controlled shutdown.
"An update will be sent if a ramp down is recommenced. There is no radiological release in progress."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE ON 8/15/10 AT 0903 EDT FROM BILL ARENS TO HUFFMAN * * *
The LLRT of valve MOV3134 was completed satisfactorily at 0500 CDT on 8/15/10. The valve was declared OPERABLE (but degraded due to the need for additional limit switch and/or torque switch adjustments that do not affect its isolation capability). At 0800 CDT, service water cooling flow was re-established to the RCP Motor Air Coolers. The current containment temperature is 120.4 degrees Fahrenheit. The licensee plans to remain at 96% power until containment temperature drops below 120 degrees.
The licensee has notified the NRC Resident Inspector. R2DO (Rudisail) notified.
"Due to failure of Service Water from RCP Motor Air Cooler valve MOV3134 to stroke satisfactorily during scheduled surveillance testing, [the licensee] entered TS 3.6.3 Condition A for Containment Isolation Valves. MOV3134 did not indicate full closed by remote indication in the Control Room when time-stroked at 0119, 8/14/10. Consequently, the isolation valve inside containment, MOV3131, was closed and deenergized to provide containment isolation. This isolated a source of Service Water cooling for containment, and the average temperature of containment started trending up from 117.5F at 0000, 8/14/10. At 1400, 8/14/10, containment average temperature exceeded 120F and entry into TS 3.6.5 Condition A was required. At 2200, 8/14/10, containment average temperature had not been restored to [less than or equal to] 120F, and TS 3.6.5 Condition B was entered. To ensure compliance with TS 3.6.5 Condition B, a ramp down to MODE 3 was initiated at 0045, 8/15/10.
"At 0057, 8/15/10, the NRC authorized enforcement discretion for Farley Nuclear Plant Unit 1 with regard to LCO 3.6.5 and containment temperature in excess of 120F. The ramp down was halted and power stabilized at 96% Rx power. The enforcement discretion duration is 18 hours starting from 2200, 8/14/10. There were two stipulations on the discretion:
"1. If the LLRT [Local Leak Rate Test] on MOV3134 fails, a controlled shutdown will be initiated. Time from the enforcement discretion will be used as necessary to achieve a controlled shutdown.
"2. If containment average temperature exceeds 122F, a controlled shutdown will be initiated. Time from the enforcement discretion will be used as necessary to achieve a controlled shutdown.
"An update will be sent if a ramp down is recommenced. There is no radiological release in progress."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE ON 8/15/10 AT 0903 EDT FROM BILL ARENS TO HUFFMAN * * *
The LLRT of valve MOV3134 was completed satisfactorily at 0500 CDT on 8/15/10. The valve was declared OPERABLE (but degraded due to the need for additional limit switch and/or torque switch adjustments that do not affect its isolation capability). At 0800 CDT, service water cooling flow was re-established to the RCP Motor Air Coolers. The current containment temperature is 120.4 degrees Fahrenheit. The licensee plans to remain at 96% power until containment temperature drops below 120 degrees.
The licensee has notified the NRC Resident Inspector. R2DO (Rudisail) notified.
Power Reactor
Event Number: 46176
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: WILLIAM BODINE
HQ OPS Officer: JOE O'HARA
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: WILLIAM BODINE
HQ OPS Officer: JOE O'HARA
Notification Date: 08/15/2010
Notification Time: 12:54 [ET]
Event Date: 08/15/2010
Event Time: 10:45 [CDT]
Last Update Date: 08/15/2010
Notification Time: 12:54 [ET]
Event Date: 08/15/2010
Event Time: 10:45 [CDT]
Last Update Date: 08/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO DISCHARGE OF AMERTAP NEOPRENE BALLS INTO WATERWAY
"During the performance of TP-1539, Unit 1 Amertap ball check on 8/15/10 at 0933, it was discovered that approximately 1300 balls could have been lost to the environment via the external circulating water system from the #12 Amertap Ball System.
"The Xcel Energy environmental service informed the plant that reports were made to the Minnesota Pollution Control Agency at 1050 CDT on 8/15/10 and the Minnesota State Duty Officer at 1045 CDT on 8/15/10.
"The Prairie Island Indian Community Tribal Council will be notified.
"The #12 Amertap Ball System is shutdown and will remain out of service until repairs are completed."
The licensee informed the NRC Resident Inspector.
"During the performance of TP-1539, Unit 1 Amertap ball check on 8/15/10 at 0933, it was discovered that approximately 1300 balls could have been lost to the environment via the external circulating water system from the #12 Amertap Ball System.
"The Xcel Energy environmental service informed the plant that reports were made to the Minnesota Pollution Control Agency at 1050 CDT on 8/15/10 and the Minnesota State Duty Officer at 1045 CDT on 8/15/10.
"The Prairie Island Indian Community Tribal Council will be notified.
"The #12 Amertap Ball System is shutdown and will remain out of service until repairs are completed."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 46177
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN MCILNAY
HQ OPS Officer: JOE O'HARA
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN MCILNAY
HQ OPS Officer: JOE O'HARA
Notification Date: 08/15/2010
Notification Time: 22:25 [ET]
Event Date: 08/15/2010
Event Time: 15:24 [EDT]
Last Update Date: 08/15/2010
Notification Time: 22:25 [ET]
Event Date: 08/15/2010
Event Time: 15:24 [EDT]
Last Update Date: 08/15/2010
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):
STEVEN RUDISAIL (R2DO)
STEVEN RUDISAIL (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 10 | Power Operation | 2 | Startup |
VALID AUX FEEDWATER SYSTEM ACTUATION DURING POWER REDUCTION FOR TURBINE MAINTENANCE
"At 1524 EDT, on 8/15/2010, Watts Bar Nuclear Plant Unit 1 had a valid actuation of the Auxiliary Feedwater System in response to a trip of all Main Feedwater Pumps. The Auxiliary Feedwater Pumps were started manually in anticipation of the trip of all Main Feedwater Pumps. Main Feedwater Pump B had been tripped manually as part of the power reduction in preparation for taking the Main Turbine offline to perform repairs on the Electrohydraulic Control System. Main Feedwater Pump A was tripped manually before it experienced a loss of suction in response to an unplanned isolation of the Intermediate Pressure Heater string.
"Following manual actuation of the Auxiliary Feedwater Pumps, reactor power was further reduced, and at 1526 [EDT], Watts Bar Unit 1entered MODE 2.
"No plant safety systems beyond Auxiliary Feedwater were required or actuated in response to this event. The plant was stabilized using Auxiliary Feedwater and the Main Steam dump valves. Operators followed their Abnormal Operating Instruction, and reactor trip was not required. This event is being reported as a valid actuation of the auxiliary feedwater system in accordance with 10 CFR 50.72(b)(3)(iv)."
Offsite power is normal and EDG's are operable.
The licensee notified the NRC Resident Inspector.
"At 1524 EDT, on 8/15/2010, Watts Bar Nuclear Plant Unit 1 had a valid actuation of the Auxiliary Feedwater System in response to a trip of all Main Feedwater Pumps. The Auxiliary Feedwater Pumps were started manually in anticipation of the trip of all Main Feedwater Pumps. Main Feedwater Pump B had been tripped manually as part of the power reduction in preparation for taking the Main Turbine offline to perform repairs on the Electrohydraulic Control System. Main Feedwater Pump A was tripped manually before it experienced a loss of suction in response to an unplanned isolation of the Intermediate Pressure Heater string.
"Following manual actuation of the Auxiliary Feedwater Pumps, reactor power was further reduced, and at 1526 [EDT], Watts Bar Unit 1entered MODE 2.
"No plant safety systems beyond Auxiliary Feedwater were required or actuated in response to this event. The plant was stabilized using Auxiliary Feedwater and the Main Steam dump valves. Operators followed their Abnormal Operating Instruction, and reactor trip was not required. This event is being reported as a valid actuation of the auxiliary feedwater system in accordance with 10 CFR 50.72(b)(3)(iv)."
Offsite power is normal and EDG's are operable.
The licensee notified the NRC Resident Inspector.