Event Notification Report for July 17, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/16/2012 - 07/17/2012
EVENT NUMBERS
4811048111481124811448116
Power Reactor
Event Number: 48110
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL CRAWFORD
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL CRAWFORD
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 07/17/2012
Notification Time: 13:23 [ET]
Event Date: 07/17/2012
Event Time: 11:18 [EDT]
Last Update Date: 07/17/2012
Notification Time: 13:23 [ET]
Event Date: 07/17/2012
Event Time: 11:18 [EDT]
Last Update Date: 07/17/2012
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):
ANTHONY DIMITRIADIS (R1DO)
ANTHONY DIMITRIADIS (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO HIGH NEUTRON FLUX
"On July 17 2012, at 1118 [EDT], Nine Mile Point Unit 1 experienced an automatic reactor scram due to high neutron flux as measured by the Average Power Range Monitoring system. The cause is currently under investigation. All control rods fully inserted and all plant systems responded per design following the scram. The High Pressure Coolant Injection [HPCI] system, which is an operating mode of the feedwater system, initiated as expected. There were no planned activities in progress at the time which could have contributed to the event.
"Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using the bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect. All emergency power sources are available in standby.
"The unit is currently implementing post scram recovery procedures."
This was an uncomplicated Reactor Scram and the plant is stable with normal levels, temperature, and pressure. Offsite power is in a normal alignment. HPCI has been secured and returned to normal alignment. The cause to the high neutron flux is still under investigation. This event had no impact on Unit 2.
The licensee has informed the NRC Resident Inspector and State Authorities.
"On July 17 2012, at 1118 [EDT], Nine Mile Point Unit 1 experienced an automatic reactor scram due to high neutron flux as measured by the Average Power Range Monitoring system. The cause is currently under investigation. All control rods fully inserted and all plant systems responded per design following the scram. The High Pressure Coolant Injection [HPCI] system, which is an operating mode of the feedwater system, initiated as expected. There were no planned activities in progress at the time which could have contributed to the event.
"Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using the bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect. All emergency power sources are available in standby.
"The unit is currently implementing post scram recovery procedures."
This was an uncomplicated Reactor Scram and the plant is stable with normal levels, temperature, and pressure. Offsite power is in a normal alignment. HPCI has been secured and returned to normal alignment. The cause to the high neutron flux is still under investigation. This event had no impact on Unit 2.
The licensee has informed the NRC Resident Inspector and State Authorities.
Power Reactor
Event Number: 48111
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: BILL HUFFMAN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/17/2012
Notification Time: 15:04 [ET]
Event Date: 07/17/2012
Event Time: 10:00 [CDT]
Last Update Date: 07/17/2012
Notification Time: 15:04 [ET]
Event Date: 07/17/2012
Event Time: 10:00 [CDT]
Last Update Date: 07/17/2012
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):
DAVID PROULX (R4DO)
DAVID PROULX (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
DEGRADED CHARGING LINE SOCKET WELDS BASED ON THERMAL FATIGUE ANALYSIS
"Results of a thermal fatigue analysis on the Chemical and Volume Control System (CVCS) charging line concluded that the socket weld fittings above the RCS piping cannot be qualified.
"As an interim action, shut down cooling purification has been secured and charging has been isolated to the RCS.
"The plant is shutdown and in Mode 5 with the reactor vessel head removed, so RCS is not intact and not required to be for current plant conditions. This report is being made in accordance with 10CFR50.72(b)(3)(ii)(A) for a degraded condition."
The licensee has notified the NRC Resident Inspector.
"Results of a thermal fatigue analysis on the Chemical and Volume Control System (CVCS) charging line concluded that the socket weld fittings above the RCS piping cannot be qualified.
"As an interim action, shut down cooling purification has been secured and charging has been isolated to the RCS.
"The plant is shutdown and in Mode 5 with the reactor vessel head removed, so RCS is not intact and not required to be for current plant conditions. This report is being made in accordance with 10CFR50.72(b)(3)(ii)(A) for a degraded condition."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48112
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: TIM HOLLAND
HQ OPS Officer: JOHN SHOEMAKER
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: TIM HOLLAND
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 07/17/2012
Notification Time: 15:18 [ET]
Event Date: 07/17/2012
Event Time: 11:40 [CDT]
Last Update Date: 07/18/2012
Notification Time: 15:18 [ET]
Event Date: 07/17/2012
Event Time: 11:40 [CDT]
Last Update Date: 07/18/2012
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):
DAVID PROULX (R4DO)
DAVID PROULX (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 |
TECHNICAL SUPPORT CENTER NON-FUNCTIONAL DUE TO DEGRADED CHARCOAL ADSORBER
"At 1140 [EDT] on Tuesday, July 17, the Callaway Plant Technical Support Center (TSC) was declared non-functional due to a degraded charcoal filter in the building's filter absorber unit. At 1140 [EDT] on July 17, 2012, Callaway was notified of the test results for a charcoal test sample that was taken on July 5, 2012. The results did not meet surveillance procedure acceptance criteria.
"Efforts are underway to replace the charcoal in the unit.
"If an emergency were to be declared requiring activation of the TSC while it is non-functional, TSC emergency response personnel would report to their backup locations in accordance with Callaway Plant emergency planning procedures.
"This notification is being made in accordance with 10 CPR 50.72(b)(3)(xiii) due to the unavailability of an emergency response facility.
"The NRC Resident Inspector has been notified." The licensee indicated the TSC will be functional within 24 hours.
* * * UPDATE AT 1012 EDT ON 07/18/12 FROM TIM HOLLAND TO JOHN KNOKE * * *
"The TSC was restored to functional status at 2200 [CDT] on July 17, 2012."
The licensee informed the NRC Resident Inspector. Notified R4DO (Walker).
"At 1140 [EDT] on Tuesday, July 17, the Callaway Plant Technical Support Center (TSC) was declared non-functional due to a degraded charcoal filter in the building's filter absorber unit. At 1140 [EDT] on July 17, 2012, Callaway was notified of the test results for a charcoal test sample that was taken on July 5, 2012. The results did not meet surveillance procedure acceptance criteria.
"Efforts are underway to replace the charcoal in the unit.
"If an emergency were to be declared requiring activation of the TSC while it is non-functional, TSC emergency response personnel would report to their backup locations in accordance with Callaway Plant emergency planning procedures.
"This notification is being made in accordance with 10 CPR 50.72(b)(3)(xiii) due to the unavailability of an emergency response facility.
"The NRC Resident Inspector has been notified." The licensee indicated the TSC will be functional within 24 hours.
* * * UPDATE AT 1012 EDT ON 07/18/12 FROM TIM HOLLAND TO JOHN KNOKE * * *
"The TSC was restored to functional status at 2200 [CDT] on July 17, 2012."
The licensee informed the NRC Resident Inspector. Notified R4DO (Walker).
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 48114
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: FRED SWIHART
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: FRED SWIHART
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/17/2012
Notification Time: 17:36 [ET]
Event Date: 07/17/2012
Event Time: 11:20 [CDT]
Last Update Date: 09/10/2012
Notification Time: 17:36 [ET]
Event Date: 07/17/2012
Event Time: 11:20 [CDT]
Last Update Date: 09/10/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
LAURA KOZAK (R3DO)
LAURA KOZAK (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
CONTROL ROOM EMERGENCY VENTILATION AC SYSTEM INOPERABLE
"On July 17, 2012, at 1120 hours the Control Room Emergency Ventilation Air Conditioning (CREV AC) system was declared inoperable due to a cooling water leak from the condenser on the Refrigeration Compressor Unit (RCU). The leakage originates from an apparent gasket leak at a bolted connection on the condenser. As a result, Technical Specification 3.7.5, Condition A, was entered. A repair plan and schedule is being developed.
"The CREV AC system maintains a habitable control room environment and ensures the operability of components in the control room emergency zone during accident conditions.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D) because the CREV system is a single train system, and loss of the CREV AC could impact the plant's ability to mitigate the consequences of an accident."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 1317 EDT ON 09/10/12 FROM DEREK DROCKELMAN TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"The purpose of this notification is to retract the ENS Report made on July 17, 2012, at 1120 hours (ENS Report # 48114).
"Further evaluation performed by Quad Cities Station confirms the CREV AC system would have performed its safety function.
"Based on this subsequent evaluation, ENS Report # 48114 is being retracted.
"Note: On July 18, 2012, the CREV AC system was successfully repaired and CREV AC system was returned to Operable status."
The licensee informed the NRC Resident Inspector. Notified R3DO (Giessner).
"On July 17, 2012, at 1120 hours the Control Room Emergency Ventilation Air Conditioning (CREV AC) system was declared inoperable due to a cooling water leak from the condenser on the Refrigeration Compressor Unit (RCU). The leakage originates from an apparent gasket leak at a bolted connection on the condenser. As a result, Technical Specification 3.7.5, Condition A, was entered. A repair plan and schedule is being developed.
"The CREV AC system maintains a habitable control room environment and ensures the operability of components in the control room emergency zone during accident conditions.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D) because the CREV system is a single train system, and loss of the CREV AC could impact the plant's ability to mitigate the consequences of an accident."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 1317 EDT ON 09/10/12 FROM DEREK DROCKELMAN TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"The purpose of this notification is to retract the ENS Report made on July 17, 2012, at 1120 hours (ENS Report # 48114).
"Further evaluation performed by Quad Cities Station confirms the CREV AC system would have performed its safety function.
"Based on this subsequent evaluation, ENS Report # 48114 is being retracted.
"Note: On July 18, 2012, the CREV AC system was successfully repaired and CREV AC system was returned to Operable status."
The licensee informed the NRC Resident Inspector. Notified R3DO (Giessner).
Power Reactor
Event Number: 48116
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: BOB MARTIN
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: BOB MARTIN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/17/2012
Notification Time: 19:32 [ET]
Event Date: 07/17/2012
Event Time: 00:00 [EDT]
Last Update Date: 07/17/2012
Notification Time: 19:32 [ET]
Event Date: 07/17/2012
Event Time: 00:00 [EDT]
Last Update Date: 07/17/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
ANTHONY DIMITRIADIS (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 50 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO SMALL RCS PRESSURE BOUNDARY INSTRUMENT LINE LEAK
"At 1715 EDT on July 17th, 2012, Calvert Cliffs Nuclear Power Plant Unit 1 identified RCS Pressure Boundary Leakage from the instrument line to 1-PDT-123A, 11A reactor coolant pump differential pressure transmitter. Technical Specification 3.4.13, Action B was entered and requires that the Unit be placed in Mode 3 within 6 hours and Mode 5 within 36 hours. The licensee has initiated plant shutdown in accordance with this Technical Specification. Therefore, this is reportable under 10 CFR 50.72(b)(2)(i) Plant Shutdown Required by Technical Specifications. This is also reportable under 50.72(B)(3)(ii)(A) as a material defect in the primary coolant system that cannot be found acceptable under ASME Section XI, IWB-3600 or ASME Section XI, Table IWB-3410-1."
The licensee initially discovered the leak during an RCS leak rate surveillance that indicated RCS leakage on the order of 0.08 gpm. A video camera was used to look for the leak and was found to be on the identified instrument line. The licensee has initiated a power reduction and is currently at approximately 50%.
The recovery plan at this time is to reduce power to about 10% which will reduce radiation levels in the area of the leak and isolate the instrument line and isolate the leakage. The instrument line is for a reactor coolant pump differential pressure transmitter which is for monitoring purposes only and does not provide any safety related functions. If the leak can be secured, the licensee intends to return to power. If the leak cannot be secured, the plant will shutdown in compliance with the technical specification action statement.
The licensee has notified the NRC Resident Inspector.
"At 1715 EDT on July 17th, 2012, Calvert Cliffs Nuclear Power Plant Unit 1 identified RCS Pressure Boundary Leakage from the instrument line to 1-PDT-123A, 11A reactor coolant pump differential pressure transmitter. Technical Specification 3.4.13, Action B was entered and requires that the Unit be placed in Mode 3 within 6 hours and Mode 5 within 36 hours. The licensee has initiated plant shutdown in accordance with this Technical Specification. Therefore, this is reportable under 10 CFR 50.72(b)(2)(i) Plant Shutdown Required by Technical Specifications. This is also reportable under 50.72(B)(3)(ii)(A) as a material defect in the primary coolant system that cannot be found acceptable under ASME Section XI, IWB-3600 or ASME Section XI, Table IWB-3410-1."
The licensee initially discovered the leak during an RCS leak rate surveillance that indicated RCS leakage on the order of 0.08 gpm. A video camera was used to look for the leak and was found to be on the identified instrument line. The licensee has initiated a power reduction and is currently at approximately 50%.
The recovery plan at this time is to reduce power to about 10% which will reduce radiation levels in the area of the leak and isolate the instrument line and isolate the leakage. The instrument line is for a reactor coolant pump differential pressure transmitter which is for monitoring purposes only and does not provide any safety related functions. If the leak can be secured, the licensee intends to return to power. If the leak cannot be secured, the plant will shutdown in compliance with the technical specification action statement.
The licensee has notified the NRC Resident Inspector.