Event Notification Report for August 31, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/30/2011 - 08/31/2011
Power Reactor
Event Number: 47224
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CECIL H. WILLIAMS, JR.
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CECIL H. WILLIAMS, JR.
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/31/2011
Notification Time: 12:02 [ET]
Event Date: 08/31/2011
Event Time: 09:06 [EDT]
Last Update Date: 08/31/2011
Notification Time: 12:02 [ET]
Event Date: 08/31/2011
Event Time: 09:06 [EDT]
Last Update Date: 08/31/2011
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):
MARVIN SYKES (R2DO)
MARVIN SYKES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
TURBINE TRIP ON HI-HI STEAM GENERATOR LEVEL RESULTS IN AUTOMATIC REACTOR TRIP
"While preparing Loop 2 Main Feed Reg Valve (MFRV) for maintenance, it was placed on its 'air gag' that maintained the MFRV in position, while any small changes in feed flow would be modulated by the associated Bypass Feed Reg Valve (BFRV). Approximately 5 minutes after the MFRV was placed on the air gag, with Steam Generator (S/G) level stable, control room operators observed S/G level start to increase. The operators observed for a short time to see if the associated BFRV would control the level change. When it became apparent that level was not being controlled automatically, the operators took manual control of the BFRV, eventually closing it all the way, and observed that S/G level was then increasing very slowly. While level was still slowly rising, two hi-hi level bistables actuated, generating a P-14 [hi-hi S/G level trip] signal which tripped the main turbine, which then caused an automatic reactor trip. As a result of the reactor trip, all systems functioned as required and there was nothing unusual or not understood."
During the transient, no safeties, primary relief valves or secondary relief valves lifted. All control rods inserted into the core. Auxiliary Feed Water automatically initiated and is supplying the steam generators. Decay heat is being removed via the steam dumps to condenser. The grid is stable with all safety buses powered from offsite power via a normal shutdown electrical lineup. Unit 2 was unaffected by the trip.
The licensee will be issuing a press release.
The NRC Resident Inspector has been notified.
"While preparing Loop 2 Main Feed Reg Valve (MFRV) for maintenance, it was placed on its 'air gag' that maintained the MFRV in position, while any small changes in feed flow would be modulated by the associated Bypass Feed Reg Valve (BFRV). Approximately 5 minutes after the MFRV was placed on the air gag, with Steam Generator (S/G) level stable, control room operators observed S/G level start to increase. The operators observed for a short time to see if the associated BFRV would control the level change. When it became apparent that level was not being controlled automatically, the operators took manual control of the BFRV, eventually closing it all the way, and observed that S/G level was then increasing very slowly. While level was still slowly rising, two hi-hi level bistables actuated, generating a P-14 [hi-hi S/G level trip] signal which tripped the main turbine, which then caused an automatic reactor trip. As a result of the reactor trip, all systems functioned as required and there was nothing unusual or not understood."
During the transient, no safeties, primary relief valves or secondary relief valves lifted. All control rods inserted into the core. Auxiliary Feed Water automatically initiated and is supplying the steam generators. Decay heat is being removed via the steam dumps to condenser. The grid is stable with all safety buses powered from offsite power via a normal shutdown electrical lineup. Unit 2 was unaffected by the trip.
The licensee will be issuing a press release.
The NRC Resident Inspector has been notified.
Agreement State
Event Number: 47233
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: PDV REFINING, LLC
Region: 3
City: LEMONT State: IL
County:
License #: IL-01603-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: STEVE SANDIN
Licensee: PDV REFINING, LLC
Region: 3
City: LEMONT State: IL
County:
License #: IL-01603-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/01/2011
Notification Time: 16:02 [ET]
Event Date: 08/31/2011
Event Time: 00:00 [CDT]
Last Update Date: 09/01/2011
Notification Time: 16:02 [ET]
Event Date: 08/31/2011
Event Time: 00:00 [CDT]
Last Update Date: 09/01/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
KEVIN HSUEH (FSME)
MICHAEL KUNOWSKI (R3DO)
KEVIN HSUEH (FSME)
AGREEMENT STATE REPORT INVOLVING A FIXED NUCLEAR GAUGE SHUTTER THAT FAILED TO CLOSE
The following information was received from the State of Illinois via email:
"Late yesterday the Agency's [Illinois Emergency Management] W. Chicago office received a call from PDV Midwest Refining (IL-01603), 135th St and New Ave., Lemont, IL 60439. The caller reported that while his crew was performing routine shutter checks of fixed gauges in his area of the plant, a shutter failed to close. The vessel the gauge was on was in use as part of a sulfur unit and needed to remain in operation with the gauge 'on-line', so no other immediate action was taken other than to advise all shift supervisors of the gauge's status and to avoid performing any work in the area.
"This morning, the radiation safety officer was contacted for additional information and instructions regarding necessary actions on their part. The RSO advised that the gauge was an Ohmart model SH-F1-45, containing 15 milliCi of Cs-137 as of April 2002. It was one of two gauges on that vessel. The other gauge which was lower on the vessel showed no difficulties in its operation. However, he noted that a similar problem had occurred in the past with the same model gauge on a parallel sulfur unit in the same physical position. At that time, field notes prepared by the manufacturer's representative who inspected the device indicated that some corrosion was present on the device. Both vessels and thus all four gauges are exposed to the full range of seasonal cycles of weather. All site staff have been made aware of the gauge condition and to ensure all 'lock out - tag out' practices are in effect in the area to preclude any work on the vessel until such time the manufacturer's rep has repaired the device or removed it from the vessel.
"The radiation safety officer was advised of the need to file a written report within 30 days in keeping with Illinois regulations.
"Source/Radioactive Material: SEALED SOURCE GAUGE Radionuclide: CS-137
"Manufacturer: OHMART CORP. Activity: 0.015 Ci [or] 0.555 GBq
"Model Number: A-2102
"Serial Number: unk
Illinois Item Number: IL11117
The following information was received from the State of Illinois via email:
"Late yesterday the Agency's [Illinois Emergency Management] W. Chicago office received a call from PDV Midwest Refining (IL-01603), 135th St and New Ave., Lemont, IL 60439. The caller reported that while his crew was performing routine shutter checks of fixed gauges in his area of the plant, a shutter failed to close. The vessel the gauge was on was in use as part of a sulfur unit and needed to remain in operation with the gauge 'on-line', so no other immediate action was taken other than to advise all shift supervisors of the gauge's status and to avoid performing any work in the area.
"This morning, the radiation safety officer was contacted for additional information and instructions regarding necessary actions on their part. The RSO advised that the gauge was an Ohmart model SH-F1-45, containing 15 milliCi of Cs-137 as of April 2002. It was one of two gauges on that vessel. The other gauge which was lower on the vessel showed no difficulties in its operation. However, he noted that a similar problem had occurred in the past with the same model gauge on a parallel sulfur unit in the same physical position. At that time, field notes prepared by the manufacturer's representative who inspected the device indicated that some corrosion was present on the device. Both vessels and thus all four gauges are exposed to the full range of seasonal cycles of weather. All site staff have been made aware of the gauge condition and to ensure all 'lock out - tag out' practices are in effect in the area to preclude any work on the vessel until such time the manufacturer's rep has repaired the device or removed it from the vessel.
"The radiation safety officer was advised of the need to file a written report within 30 days in keeping with Illinois regulations.
"Source/Radioactive Material: SEALED SOURCE GAUGE Radionuclide: CS-137
"Manufacturer: OHMART CORP. Activity: 0.015 Ci [or] 0.555 GBq
"Model Number: A-2102
"Serial Number: unk
Illinois Item Number: IL11117