Event Notification Report for April 10, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/09/2009 - 04/10/2009
Power Reactor
Event Number: 44982
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRAIN FINCH
HQ OPS Officer: JASON KOZAL
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRAIN FINCH
HQ OPS Officer: JASON KOZAL
Notification Date: 04/10/2009
Notification Time: 12:43 [ET]
Event Date: 04/10/2009
Event Time: 05:38 [EDT]
Last Update Date: 04/10/2009
Notification Time: 12:43 [ET]
Event Date: 04/10/2009
Event Time: 05:38 [EDT]
Last Update Date: 04/10/2009
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):
LAWRENCE DOERFLEIN (R1)
LAWRENCE DOERFLEIN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 28 | Power Operation | 23 | Power Operation |
HIGH PRESSURE COOLANT INJECTION AUTOMATIC INITIATION DUE TO TURBINE TRIP
"At 0538 on Friday, April 10, 2009, Nine Mile Point Unit One manually tripped the turbine at approximately 28% rated power in response to rising turbine bearing vibrations. Following the manual turbine trip, the High Pressure Coolant Injection (HPCI) system automatically initiated on the turbine trip signal. The HPCI system initiation signal was reset immediately following the turbine trip. Reactor water level was maintained in the normal operating range throughout the transient. At Nine Mile Point Unit One the HPCI system is a mode of operation of the feedwater and condensate system. It is not an Emergency Core Cooling System (ECCS). A HPCI system actuation signal on a turbine trip is an expected response of the HPCI system. Nine Mile Point Unit 1 remains at power since the turbine was tripped at a power level that is within the capacity of the turbine bypass valves.
"10 CFR 50.72(b)(3)(iv)(A) requires reporting within 8 hours when a valid actuation of the feedwaler coolant injection system occurs.
"The event has been entered into the corrective action program.
"There are no other adverse impacts to the station based on this event."
The NRC Resident Inspector was notified.
"At 0538 on Friday, April 10, 2009, Nine Mile Point Unit One manually tripped the turbine at approximately 28% rated power in response to rising turbine bearing vibrations. Following the manual turbine trip, the High Pressure Coolant Injection (HPCI) system automatically initiated on the turbine trip signal. The HPCI system initiation signal was reset immediately following the turbine trip. Reactor water level was maintained in the normal operating range throughout the transient. At Nine Mile Point Unit One the HPCI system is a mode of operation of the feedwater and condensate system. It is not an Emergency Core Cooling System (ECCS). A HPCI system actuation signal on a turbine trip is an expected response of the HPCI system. Nine Mile Point Unit 1 remains at power since the turbine was tripped at a power level that is within the capacity of the turbine bypass valves.
"10 CFR 50.72(b)(3)(iv)(A) requires reporting within 8 hours when a valid actuation of the feedwaler coolant injection system occurs.
"The event has been entered into the corrective action program.
"There are no other adverse impacts to the station based on this event."
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 44983
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: MICHAEL MCBEARTY
HQ OPS Officer: JASON KOZAL
Region: 4 State: CA
Unit: [] [] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: MICHAEL MCBEARTY
HQ OPS Officer: JASON KOZAL
Notification Date: 04/10/2009
Notification Time: 18:21 [ET]
Event Date: 04/10/2009
Event Time: 09:00 [PDT]
Last Update Date: 04/10/2009
Notification Time: 18:21 [ET]
Event Date: 04/10/2009
Event Time: 09:00 [PDT]
Last Update Date: 04/10/2009
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):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO SULFURIC ACID OVERFLOW
"On Friday April 10, 2009, at about 0900 PDT, Southern California Edison (SCE) discovered that approximately 1,000 gallons of sulfuric acid had overflowed from the Unit 3 Sulfuric Acid Day Tank. The acid was contained within a berm around the tank, and there was no release to the environment. SONGS (San Onofre Nuclear Generating Station) Hazardous Materials personnel responded to the event, and are in the process of removing the acid from the berm for disposal at a hazardous waste facility. The overflow was caused by leakage from the Bulk Acid Tank to the Acid Day Tank.
"At about 1340 PDT, SCE notified the San Diego County Department of Environmental Health, and at about 1353 PDT, SCE notified the California Office of Emergency Services.
"SCE is making this notification in accordance with 10CFR50.72(b)(2)(xi).
"At the time of this report, SONGS Unit 2 is in Mode 1 at approximately 99% power and Unit 3 is in Mode 1 at approximately 100% power. The NRC Senior Resident Inspector has been notified of this occurrence and will be provided with a copy of this report."
"On Friday April 10, 2009, at about 0900 PDT, Southern California Edison (SCE) discovered that approximately 1,000 gallons of sulfuric acid had overflowed from the Unit 3 Sulfuric Acid Day Tank. The acid was contained within a berm around the tank, and there was no release to the environment. SONGS (San Onofre Nuclear Generating Station) Hazardous Materials personnel responded to the event, and are in the process of removing the acid from the berm for disposal at a hazardous waste facility. The overflow was caused by leakage from the Bulk Acid Tank to the Acid Day Tank.
"At about 1340 PDT, SCE notified the San Diego County Department of Environmental Health, and at about 1353 PDT, SCE notified the California Office of Emergency Services.
"SCE is making this notification in accordance with 10CFR50.72(b)(2)(xi).
"At the time of this report, SONGS Unit 2 is in Mode 1 at approximately 99% power and Unit 3 is in Mode 1 at approximately 100% power. The NRC Senior Resident Inspector has been notified of this occurrence and will be provided with a copy of this report."
Research Reactor
Event Number: 44991
Rep Org: NORTH CAROLINA STATE UNIVERSITY
Licensee: NORTH CAROLINA STATE UNIVERSITY
Region: 2
City: RALEIGH State: NC
County: WAKE
License #: R-120
Agreement: Y
Docket: 05000297
NRC Notified By: GERALD WICKS
HQ OPS Officer: JOHN KNOKE
Licensee: NORTH CAROLINA STATE UNIVERSITY
Region: 2
City: RALEIGH State: NC
County: WAKE
License #: R-120
Agreement: Y
Docket: 05000297
NRC Notified By: GERALD WICKS
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/14/2009
Notification Time: 16:00 [ET]
Event Date: 04/10/2009
Event Time: 09:30 [EDT]
Last Update Date: 04/14/2009
Notification Time: 16:00 [ET]
Event Date: 04/10/2009
Event Time: 09:30 [EDT]
Last Update Date: 04/14/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MALCOLM WIDMANN (R2)
DUANE HARDESTY (NRR)
MALCOLM WIDMANN (R2)
DUANE HARDESTY (NRR)
VIOLATION OF LIMITING CONDITIONS IN TECHNICAL SPECIFICATION 3.5B
"On Monday, 13 Apr 2009 at approximately 9 AM, the stack sample pump was observed to be off. On Friday, 10 Apr 2009, the reactor operated from approximately 11 AM to 4 PM.
"Upon investigating this situation it was learned that at approximately 9:30 AM on 10 Apr 2009 the stack sample pump apparently lost power. The stack pump remained off until being re-started on 13 Apr 2009.
"Technical Specification (TS) 3.5b requires the stack particulate and stack gas radiation monitoring channels to be operable during reactor operation. With the stack sample pump off, neither of these two channels were operable during reactor operation on 10 Apr 2009. The Auxiliary GM may serve as a substitute for one of the two required channels. As a result, the reactor was operated on 10 Apr 2009 in violation of TS 3.5b.
"This event is a reportable event as defined in TS (1.2.24d and 6.6.2) under TS 6.7.1 since both channels were not operable as required by the Limiting Conditions for Operation TS 3.5b. The US Nuclear Regulatory Commission (NRC) was notified by telephone on 14 Apr 2009 at approximately 4 PM. The event will be investigated further with a detailed explanation of the event and actions taken and planned to prevent recurrence. The NRC will be given a written report on or before 24 Apr 2009.
"Consequences of this event were not significant. Other radiation monitors were in service to monitor airborne radioactive effluent and reactor bay airborne activity. All of those monitors indicated typical radiation levels during reactor operation."
"On Monday, 13 Apr 2009 at approximately 9 AM, the stack sample pump was observed to be off. On Friday, 10 Apr 2009, the reactor operated from approximately 11 AM to 4 PM.
"Upon investigating this situation it was learned that at approximately 9:30 AM on 10 Apr 2009 the stack sample pump apparently lost power. The stack pump remained off until being re-started on 13 Apr 2009.
"Technical Specification (TS) 3.5b requires the stack particulate and stack gas radiation monitoring channels to be operable during reactor operation. With the stack sample pump off, neither of these two channels were operable during reactor operation on 10 Apr 2009. The Auxiliary GM may serve as a substitute for one of the two required channels. As a result, the reactor was operated on 10 Apr 2009 in violation of TS 3.5b.
"This event is a reportable event as defined in TS (1.2.24d and 6.6.2) under TS 6.7.1 since both channels were not operable as required by the Limiting Conditions for Operation TS 3.5b. The US Nuclear Regulatory Commission (NRC) was notified by telephone on 14 Apr 2009 at approximately 4 PM. The event will be investigated further with a detailed explanation of the event and actions taken and planned to prevent recurrence. The NRC will be given a written report on or before 24 Apr 2009.
"Consequences of this event were not significant. Other radiation monitors were in service to monitor airborne radioactive effluent and reactor bay airborne activity. All of those monitors indicated typical radiation levels during reactor operation."