Event Notification Report for August 12, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/11/2012 - 08/12/2012
Power Reactor
Event Number: 48181
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RICHARD VIGNEAH
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RICHARD VIGNEAH
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/12/2012
Notification Time: 01:48 [ET]
Event Date: 08/12/2012
Event Time: 00:44 [EDT]
Last Update Date: 08/12/2012
Notification Time: 01:48 [ET]
Event Date: 08/12/2012
Event Time: 00:44 [EDT]
Last Update Date: 08/12/2012
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):
ART BURRITT (R1DO)
ART BURRITT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 66 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO ULTIMATE HEAT SINK EXCEEDING TEMPERATURE LIMIT
Millstone Unit 2 reported that it is in a technical specification shutdown condition based on the ultimate heat sink average water temperature exceeding a temperature limit of 75 degrees Fahrenheit. The ultimate heat sink is supplied by water from Niantic Bay. At the time of this report, the bay water temperature is slightly below the 75 degree temperature limit but the time average calculation for the ultimate heat sink temperature limit still exceeds 75 degrees.
The Ultimate Heat Sink Technical Specification, TS 3.7.11.a, requires the unit to be in hot shutdown within 6 hours when the average temperature limit is exceeded. The licensee is in a slow power ramp-down while monitoring the ultimate heat sink average temperature for water temperature conditions to drop below the limit. The high heat sink temperatures are based on natural environmental conditions and not from plant operation.
Millstone Unit 3 is not impacted at this time.
The licensee has notified State and local authorities and will notify the NRC Resident Inspector.
* * * UPDATE AT 0518 EDT ON 8/12/12 FROM WOLLERY TO HUFFMAN * * *
The licensee reported that it had exited the Technical Specification LCO based on a current average heat sink temperature below 75 F. However, the licensee will hold power at 65% to ensure the temperature is stable and will remain below the limit during the day shift.
The licensee has notified the NRC Resident Inspector. R1DO (Burritt) notified.
* * * UPDATE AT 1001 EDT ON 8/12/12 FROM NICHOLS TO HUFFMAN * * *
At 0943 EDT on 8/12/12, the average ultimate heat sink temperature on Unit 2 exceeded the 75 degree limit again. The licensee re-entered TS LCO 3.7.11.a and commenced to shutdown the unit from a starting power level of 65%. The licensee plans to proceed to Hot Standby in compliance with the TS action statement even if the heat sink temperature drops back below the TS limit.
The licensee has notified State and local authorities and the NRC Resident Inspector. R1DO (Burritt) notified.
* * * UPDATE AT 1650 EDT ON 8/12/12 FROM PATRICK SIKORSKI TO JOHN KNOKE * * *
At 1645 EDT on 8/12/12, Unit 2 is in Hot Standby and the heat sink temperature is below the 75 degree limit.
The licensee has notified State and local authorities and the NRC Resident Inspector. R1DO (Burritt) notified.
Millstone Unit 2 reported that it is in a technical specification shutdown condition based on the ultimate heat sink average water temperature exceeding a temperature limit of 75 degrees Fahrenheit. The ultimate heat sink is supplied by water from Niantic Bay. At the time of this report, the bay water temperature is slightly below the 75 degree temperature limit but the time average calculation for the ultimate heat sink temperature limit still exceeds 75 degrees.
The Ultimate Heat Sink Technical Specification, TS 3.7.11.a, requires the unit to be in hot shutdown within 6 hours when the average temperature limit is exceeded. The licensee is in a slow power ramp-down while monitoring the ultimate heat sink average temperature for water temperature conditions to drop below the limit. The high heat sink temperatures are based on natural environmental conditions and not from plant operation.
Millstone Unit 3 is not impacted at this time.
The licensee has notified State and local authorities and will notify the NRC Resident Inspector.
* * * UPDATE AT 0518 EDT ON 8/12/12 FROM WOLLERY TO HUFFMAN * * *
The licensee reported that it had exited the Technical Specification LCO based on a current average heat sink temperature below 75 F. However, the licensee will hold power at 65% to ensure the temperature is stable and will remain below the limit during the day shift.
The licensee has notified the NRC Resident Inspector. R1DO (Burritt) notified.
* * * UPDATE AT 1001 EDT ON 8/12/12 FROM NICHOLS TO HUFFMAN * * *
At 0943 EDT on 8/12/12, the average ultimate heat sink temperature on Unit 2 exceeded the 75 degree limit again. The licensee re-entered TS LCO 3.7.11.a and commenced to shutdown the unit from a starting power level of 65%. The licensee plans to proceed to Hot Standby in compliance with the TS action statement even if the heat sink temperature drops back below the TS limit.
The licensee has notified State and local authorities and the NRC Resident Inspector. R1DO (Burritt) notified.
* * * UPDATE AT 1650 EDT ON 8/12/12 FROM PATRICK SIKORSKI TO JOHN KNOKE * * *
At 1645 EDT on 8/12/12, Unit 2 is in Hot Standby and the heat sink temperature is below the 75 degree limit.
The licensee has notified State and local authorities and the NRC Resident Inspector. R1DO (Burritt) notified.
Power Reactor
Event Number: 48182
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TODD MULFORD
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TODD MULFORD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/12/2012
Notification Time: 11:05 [ET]
Event Date: 08/12/2012
Event Time: 04:18 [EDT]
Last Update Date: 08/12/2012
Notification Time: 11:05 [ET]
Event Date: 08/12/2012
Event Time: 04:18 [EDT]
Last Update Date: 08/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (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 |
DEGRADED CONDITION REPORTED BASED ON THE DISCOVERY OF PRESSURE BOUNDARY LEAKAGE
"Following a planned shutdown to investigate the source of elevated Primary Coolant System (PCS) Unidentified Leakage, the Mode 3 PCS walk-down identified a steam leak on CRD-24, Control Rod Drive Mechanism (CRD), pressure housing. The leak is ~ 1 foot above the CRD to Reactor Head flange. The leak was observed from the Refueling floor deck and appears to be coming from an area of the CRD with no bolted connections. Leakage from this area is unexpected and the mechanism of failure is not understood at this time. Closer examination of the leak is expected to occur in parallel with plant cool-down.
"The plant entered T.S. 3.4.14 (PCS Operational Leakage) Condition B. at 0418 EDT hours this morning and this requires the plant to be placed in Mode 5 within 36 hours. The leakage is considered Pressure Boundary Leakage. Operations is in progress of performing the plant cool-down from Mode 3 to Mode 5."
The licensee discovered this condition following a shutdown the morning of 8/12/12 to investigate unidentified primary coolant leakage of about 0.3 gpm that had been recently trending upwards. Plant conditions are currently 400 degrees F with primary system pressure at about 1000 psi.
The licensee has notified the NRC Resident Inspect
"Following a planned shutdown to investigate the source of elevated Primary Coolant System (PCS) Unidentified Leakage, the Mode 3 PCS walk-down identified a steam leak on CRD-24, Control Rod Drive Mechanism (CRD), pressure housing. The leak is ~ 1 foot above the CRD to Reactor Head flange. The leak was observed from the Refueling floor deck and appears to be coming from an area of the CRD with no bolted connections. Leakage from this area is unexpected and the mechanism of failure is not understood at this time. Closer examination of the leak is expected to occur in parallel with plant cool-down.
"The plant entered T.S. 3.4.14 (PCS Operational Leakage) Condition B. at 0418 EDT hours this morning and this requires the plant to be placed in Mode 5 within 36 hours. The leakage is considered Pressure Boundary Leakage. Operations is in progress of performing the plant cool-down from Mode 3 to Mode 5."
The licensee discovered this condition following a shutdown the morning of 8/12/12 to investigate unidentified primary coolant leakage of about 0.3 gpm that had been recently trending upwards. Plant conditions are currently 400 degrees F with primary system pressure at about 1000 psi.
The licensee has notified the NRC Resident Inspect
Power Reactor
Event Number: 48183
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: STEPHEN FLESHMAN
HQ OPS Officer: JOHN KNOKE
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: STEPHEN FLESHMAN
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/12/2012
Notification Time: 14:37 [ET]
Event Date: 08/12/2012
Event Time: 12:34 [EDT]
Last Update Date: 08/12/2012
Notification Time: 14:37 [ET]
Event Date: 08/12/2012
Event Time: 12:34 [EDT]
Last Update Date: 08/12/2012
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):
ART BURRITT (R1DO)
ART BURRITT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 80 | Power Operation |
TECHNICAL SPECIFICATION SHUTDOWN DUE TO FULLY INSERTED CONTROL ROD WHILE OPERATING
"Calvert Cliff Nuclear Power Plant, Unit 1 Control Element Assembly (CEA) #9 fully inserted (CEA dropped) into the core. Technical Specification 3.1.5, Action B was entered and requires the CEA to be realigned within 2 hours. With this action not met Technical Specification 3.1.5, Action C requires the Unit be placed in Mode 3 within 6 hours. A plant shutdown has been initiated in accordance with this Technical Specification. Therefore, this is reportable under 10 CFR 50.72. (b) (2) (i) Plant Shutdown Required by Technical Specifications."
The licensee has notified the NRC Resident Inspector. The licensee will also notify local government agencies.
"Calvert Cliff Nuclear Power Plant, Unit 1 Control Element Assembly (CEA) #9 fully inserted (CEA dropped) into the core. Technical Specification 3.1.5, Action B was entered and requires the CEA to be realigned within 2 hours. With this action not met Technical Specification 3.1.5, Action C requires the Unit be placed in Mode 3 within 6 hours. A plant shutdown has been initiated in accordance with this Technical Specification. Therefore, this is reportable under 10 CFR 50.72. (b) (2) (i) Plant Shutdown Required by Technical Specifications."
The licensee has notified the NRC Resident Inspector. The licensee will also notify local government agencies.