| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/13/2011 - 06/14/2011 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 46734 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: CHEVRON PRODUCTS COMPANY
Region: 4
City: PASCAGOULA State: MS
County:
License #: MS-413-01
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: JOE O'HARA | Notification Date: 04/06/2011
Notification Time: 17:50 [ET]
Event Date: 03/22/2011
Event Time: [CDT]
Last Update Date: 06/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4DO)
PAUL MICHALAK (FSME)
| Event Text AGREEMENT STATE REPORT - SOURCE DISLODGED FROM OHMART VEGA MODEL SHLM-BR
The following was received via e-mail:
"Licensee's RSO notified DRH [state] by phone on 3-22-11, and by letter received on 3-22-11, of a dislodged source from an Ohmart Vega Model SHLM-BR, fixed gauge Ser. No. 13530993. The source became dislodged from the main rod during the gauge's shutter test and fell into the gauge well. The licensee's surveys around the gauge well were less than 0.5 mR/hr. A gauge representative has been called in to repair the gauge.
"DRH [state] requested licensee send in manufacturer's service report with the licensee's written 30-day report."
The source is 40 millicurie Cs-137, ser. No. 6965GK.
Mississippi Incident Number MS-11004.
* * * UPDATE FROM JAYSON MOAK TO JOE O'HARA VIA E-MAIL AT 1200 EDT ON 4/7/11 * * *
"Licensee was contacted [by the state] on 4/7/11, for further clarification of the location of the source. The licensee's RSO said the source was at the bottom of the well inside a vessel. This would also be the case during normal operations. Surveys were also confirmed by the RSO to be 0.5 mR/hr around the vessel. Licensee's RSO said a new well is being built for the vessel and a service representative has been notified. Source retrieval and replacement of the gauge is scheduled for the middle of April once the new well is built, and the material in the vessel has cooled."
Notified R4DO(O'Keefe) and FSME(McIntosh)
* * * UPDATE AT 1603 ON 6/13/2011 FROM JAYSON MOAK TO MARK ABRAMOVITZ * * *
The following information was received via e-mail:
"Licensee submitted a field service report from the gauge service company on 6/9/2011. The service report indicated the roll pin in the rod was sheared and the source carrier fell to the bottom of the well. The service report claimed the roll pin was corroded due to the harsh environment that the source was in. Part of the rod was still attached to the source which was retrieved and inserted back into the source holder. The source was replaced, and the old source has been transferred."
Notified the R4DO (Werner) and FSME (Persinko). |
| Agreement State | Event Number: 46938 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: BIG RIVERS ELECTRIC CO-OP
Region: 1
City: SEBREE State: KY
County:
License #: KY 201-208-56
Agreement: Y
Docket:
NRC Notified By: MELVIN GOODFRIEND
HQ OPS Officer: CHARLES TEAL | Notification Date: 06/09/2011
Notification Time: 09:10 [ET]
Event Date: 06/08/2011
Event Time: 12:00 [CDT]
Last Update Date: 06/09/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN ROGGE (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE - SHUTTER SEPARATED FROM GAUGE
The following was received via fax:
While removing the gauge the shutter became partially separated from the body. The source did not leave the gauge. The operator placed the gauge face down on the shutter assembly in a lead lined transport box. The gauge was surveyed and the max radiation field was 0.026 mR/hr. There was no exposure to personnel. The area was cordoned off and the manufacturer was notified to package and transport the device.
The gauge was a Texas Nuclear Model 5193 S/N Bi449. |
| Power Reactor | Event Number: 46951 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEN HILL
HQ OPS Officer: CHARLES TEAL | Notification Date: 06/13/2011
Notification Time: 10:17 [ET]
Event Date: 06/13/2011
Event Time: 05:10 [CDT]
Last Update Date: 06/13/2011 | 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
| Person (Organization):
JULIO LARA (R3DO)
LAURA KOZAK (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M | Y | 34 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO STEAM LEAK IN TURBINE BUILDING
"On June 13, 2011 at 0510 CDT, a manual scram was inserted on Unit 1 following discovery of a steam leak in the turbine building downstream of the Main Turbine Stop Valves. Following the reactor scram, reactor water level decreased to approximately -19 inches, which resulted in automatic Group II and Group III isolations (expected response). The steam leak was isolated by closure of the Main Turbine Stop Valves. All systems responded properly to the event. Unit 1 remains in Mode 3 [hot shutdown], maintaining reactor pressure with the Main Turbine Bypass Valves; reactor water level is in the normal level band. The cause of the event is still under investigation."
"Unit 2 was unaffected by the event and remains at 100% power."
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46953 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ROBERT KROS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 06/13/2011
Notification Time: 14:30 [ET]
Event Date: 06/13/2011
Event Time: 12:00 [CDT]
Last Update Date: 06/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GREG WERNER (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 | Event Text OFFSITE NOTIFICATION DUE TO SEWAGE SYSTEM RELEASE
"At 0500 CDT, the lift station #4 sewage system, South of the Fort Calhoun Station Administration building, was released to the Missouri River. The release was a mixture of ground water and sewage; samples were taken by chemistry but dilution concentration is unknown. Approximately 105 gpm release started around 0500 on 6/13/2011. This condition is being reported pursuant to 10 CFR 50.72(b)(2)(xi) for an event related to the protection of the environment for which a notification of governmental agencies is required. Applicable governmental agencies have been notified per plant procedures."
The licensee notified the State of Nebraska at 1200 CDT. The licensee also notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46954 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BOB MURRELL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/13/2011
Notification Time: 15:19 [ET]
Event Date: 04/14/2011
Event Time: 20:43 [CDT]
Last Update Date: 06/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
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 | Event Text INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION DUE TO CONNECTOR HIGH RESISTANCE
"This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73(a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system.
"At 2043 on April 14, 2011, with the Duane Arnold Energy Center (DAEC) operating at 100% power, an invalid Group 3 isolation on the 'A' side of the Primary Containment Isolation System occurred. Group 3 isolation signals were generated for Primary Containment Isolation Valves for Drywell and Torus Ventilation, and Purge, Containment Nitrogen Compressor Suction and Discharge, Recirculation Pump Seals, and Post Accident Sample System.
"This event was caused by a high resistance contact on connectors in the detector circuitry for the 'A' Reactor Building Vent Shaft Radiation Monitor.
"All equipment responded in accordance with the plant design. Specifically, all actuations were complete and successful.
"There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution.
"The licensee notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 46955 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: SANDRA SEVERANCE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/13/2011
Notification Time: 16:04 [ET]
Event Date: 06/07/2011
Event Time: 11:52 [EDT]
Last Update Date: 06/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
MIKE ERNSTES (R2DO)
PART 21 GROUP ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text NONCONSERVATIVE VALVE ACTUATOR PROGRAM SOFTWARE
"In Kalsi Engineering Valve and Actuator Program (KVAP) Error Report 2011-02, Kalsi Engineering identified an error in the KVAP software that provides default flow and torque coefficients for ball and plug valves which can affect margin predictions. Communication between Kalsi and Duke Energy personnel confirmed that non-conservative torque values were calculated for select ball valves used at Oconee for containment isolation. As a result of the Kalsi error, the non-conservatively calculated torque values resulted in negative actuator margins, calling into question the actuators' capability to close the valves under all design conditions. Therefore, it has been determined that the KVAP software program error constitutes a defect, reportable under 10CFR21.
"Four safety-related containment isolation valves in the High Pressure Injection system were impacted, requiring entry into TS 3.6.3, Containment Isolation Valves, on two Oconee units [Units 2 and 3]."
Unit 1 was shutdown for a refueling outage at the time of this event and the actuator spring was replaced during the outage. The valves on units 2 and 3 required a Notification of Enforcement Discretion (NOED) which occurred on June 2, 2011. Three of the four valves were declared operable on June 10, 2011 and the remaining valve was declared operable the next day.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46957 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DAVID PLESSAS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/13/2011
Notification Time: 23:29 [ET]
Event Date: 06/13/2011
Event Time: 19:24 [CDT]
Last Update Date: 06/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
LAURA KOZAK (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 0 | Startup | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DURING STARTUP PHYSICS TESTING
"On June 13, 2011 at 1924 CDT, an automatic reactor trip was actuated during Shutdown Bank Insertion for Beginning of Life Physics Testing. Neutron flux lowered from the intermediate range to the point of automatic energization of the Source Range Nuclear Instruments. Energization of the Source Range Nuclear Instruments during this step is anticipated and permissible per the test procedure. When it energized, the N-31 Source Range Nuclear Instrument (Red Channel) failed high which initiated an automatic reactor trip.
"All plant systems functioned as required, including the Reactor Protection System. All control rods fully inserted into the core. There was no Emergency Core Cooling System or Auxiliary Feedwater System actuation. No Emergency Diesel Generators were started and power continues to be supplied from off site. The reactor coolant system has forced circulation and the atmospheric steam dumps are currently being used for decay heat removal from the steam generators.
"There was no radiological release and emergency plan implementation was not required.
"An investigation of the failure of the N-31 Source Range Nuclear Instrument is in progress"
There is no known primary to secondary leakage. The licensee notified the NRC Resident Inspector. | |