| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/13/2012 - 12/14/2012 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 48562 | Rep Org: ARCELORMITTAL
Licensee: ARCELORMITTAL
Region: 3
City: EAST CHICAGO State: IN
County:
License #: 13-03086-03
Agreement: N
Docket:
NRC Notified By: SACOTT BUSH
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/05/2012
Notification Time: 17:10 [ET]
Event Date: 12/05/2012
Event Time: 12:00 [EST]
Last Update Date: 12/05/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text FIXED GAUGE SHUTTER FAILED TO CLOSE
During a maintenance outage, the shutter on a fixed gauge failed to close. The specific gauge information is as follows:
Make: Texas Nuclear
Model: 5010
Source: 1000mCi Am-241/Be
The gauge is used for weighing purposes. The licensee has contacted the manufacturer, Thermo Fisher, who is scheduled to arrive on-site at 1000 EST on 12/6/12. There were no personnel exposures involved and the area containing the gauge has been posted to prevent employees from entering inadvertently. |
| Part 21 | Event Number: 48585 | Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE E. PORTER
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/13/2012
Notification Time: 08:41 [ET]
Event Date: 12/13/2012
Event Time: [EST]
Last Update Date: 12/13/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
DANIEL HOLODY (R1DO)
ALAN BLAMEY (R2DO)
JAMNES CAMERON (R3DO)
MARK HAIRE (R4DO)
NRR PART 21 (EMAI)
| Event Text 60-DAY INTERIM REPORT INVOLVING AN EVALUATION OF A DESIGN CHANGE TO MAGNE-BLAST CIRCUIT BREAKERS
The following information was received via fax:
"Summary
"GE Hitachi Nuclear Energy (GEH) is investigating the adequacy of a Design Change in AM 4.16-350-2C and AM 4.16-350-2H Magne-Blast Circuit Breakers as a result of a breaker failure at a BWR Licensee.
"GEH has not completed the evaluation of this condition to determine reportability under 10 CFR Part 21 and is therefore issuing this 60-day Interim Notification. GEH will close or issue an update on this matter on or before June 14, 2013. Given the early status of the evaluation, GEH has no recommended actions at this time. This 60-day Interim Notification is issued in accordance with 10 CFR Part 21.21(a)(2), and will be sent to all GE BWR/2-6 plants and all PWRs.
"Recommendation
"GEH advises licensees to take no action at this time. However, if licensees wish to determine if the extent of this issue is present at their respective plants, they may identify breaker models AM 4.16-350-2H/2C with a date of manufacture prior to October 6, 1971. Other AM breaker styles do not use the booster cylinder as designed in breaker model AM 4.16-350-2H/2C and are not included in this concern. Therefore the extent is limited to the AM 4.16-350-2H/2C models manufactured prior to October 6, 1971.
"US Plants Potentially Affected
"Nine Mile Point 1-2, Fermi 2, Columbia, Grand Gulf, River Bend, FitzPatrick, Pilgrim, Vermont Yankee, Clinton, Dresden 2-3, LaSalle 1-2, Limerick 1-2, Oyster Creek, Peach Bottom 2-3, Quad Cities 1-2, Perry 1, Duane Arnold, Cooper, Susquehanna 1-2, Brunswick 1-2, Hope Creek, Hatch 1 - 2, Browns Ferry 1-3, Monticello, Callaway, Palo Verde 1-3 , Calvert Cliffs 1-2, Ginna, Arkansas Nuclear One 1-2, Indian Point 2-3, Millstone 2, Millstone 3, North Anna 1-2, Palisades, Surry 1-2, Waterford 3, Catawba 1-2, Oconee 1-3, McGuire 1-2, Braidwood 1-2, Exelon Byron 1-2 , Three Mi le Island 1, Beaver Valley 1-2, Davis-Besse, Seabrook, St. Lucie 1-2, Turkey Point 3-4, Point Beach 1-2, DC Cook 1-2, Prairie Island 1-2, Fort Calhoun, Diablo Canyon 1-2, Crystal River 3, Robinson, Shearon Harris, Salem 1, Salem 2, Summer, South Texas Project 1-2, San Onofre 2-3, Farley 1-2, Vogtle 1-2, Sequoyah 1-2, Watts Bar 1, Comanche Peak 1-2, and Wolf Creek.
"If you have an questions, please call me at (910) 819-4491.
Dale E. Porter
Safety Evaluation Program Manager
GE-Hitachi Nuclear Energy Americas LLC"
Hitachi Reference Number: MFN-128 R0 |
| Power Reactor | Event Number: 48586 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: NICHOLAS DeSANTIS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 12/13/2012
Notification Time: 08:58 [ET]
Event Date: 12/13/2012
Event Time: 08:55 [EST]
Last Update Date: 12/13/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ALAN BLAMEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 99 | Power Operation | 99 | Power Operation | | 4 | N | N | 0 | Defueled | 0 | Defueled | Event Text TECHNICAL SUPPORT CENTER VENTILATION SYSTEM REMOVED FROM SERVICE FOR MAINTENANCE
"Planned maintenance activities are being performed today (December 13, 2012) to Technical Support Center (TSC) HVAC. This work activity is planned to be performed and completed expeditiously within about 8 hours including establishing and removing the clearances, and performing post maintenance testing.
"If an emergency condition occurs that requires activation of the TSC, plans are to utilize the TSC during the time this work activity is being performed, as long as habitability conditions allow. The Emergency Response Organization duty team members will be relocated to alternate locations if required by habitability conditions in accordance with emergency implementing procedures.
"This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM JOSEPH MCKED TO JOHN KNOKE AT 2000 EST ON 12/13/12 * * *
The licensee reported that the planned maintenance activities have been completed to the Technical Support Center's HVAC.
The licensee has notified the NRC Resident Inspector.
R2DO (Blamey) notified. |
| Power Reactor | Event Number: 48587 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: BILL BALL
HQ OPS Officer: BILL HUFFMAN | Notification Date: 12/13/2012
Notification Time: 10:28 [ET]
Event Date: 10/17/2012
Event Time: 23:01 [CST]
Last Update Date: 12/13/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
ALAN BLAMEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text 60-DAY TELEPHONE NOTIFICATION OF AN INVALID SYSTEM ACTUATION
"This 60-day telephone notification is being made in accordance with the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of a general containment isolation signal affecting more than one system.
"On October 17, 2012, at 2301 hours Central Daylight Time (CDT), the 3A Reactor Protection System (RPS) Motor Generator (MG) Set tripped, causing the loss of the 3A RPS Bus, resulting in a half scram. Loss of the 3A RPS Bus automatically isolated Primary Containment Isolation System (PCIS) groups 2, 3, 6, and 8 which initiated 'A' Train of Control Room Emergency Ventilation (CREV) and 'A', 'B', and 'C' Trains of Standby Gas Treatment (SGT) while isolating the Reactor Water Cleanup System (RWCU).
"Plant Conditions which initiate PCIS Group 2 actuations are Reactor Vessel Low Water Level, High Drywell Pressure, or Reactor Vessel High Pressure. The PCIS Group 3 actuations are initiated by Reactor Vessel Low Water Level or Reactor Water Cleanup Area High Temperature. The PCIS Group 6 actuations are initiated by Reactor Vessel Low Water Level, High Drywell Pressure, or Reactor Building Ventilation Exhaust High Radiation (Reactor Zone or Refuel Zone). The PCIS Group 8 actuations are initiated by Low Reactor Vessel Water Level or High Drywell Pressure. At the time of the event, these conditions did not exist; therefore, the actuation of the PCIS was invalid.
"The affected equipment responded as designed.
"This condition was caused by the 3A RPS MG-Set motor winding's insulation failing due to age related degradation. To correct this condition, the 3A RPS MG Set was removed, rewound, refurbished, and re-installed.
"There were no safety consequences or impact to the health and safety of the public as a result of this event.
"This event was entered into the Corrective Action Program as Problem Evaluation Report 625651.
"The NRC Resident Inspector has been notified of this event." |
| Power Reactor | Event Number: 48588 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: MIKE NOVAK
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/13/2012
Notification Time: 13:10 [ET]
Event Date: 12/13/2012
Event Time: 11:00 [EST]
Last Update Date: 12/13/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ALAN BLAMEY (R2DO)
|
| 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 SEISMIC MONITORING SYSTEM INOPERABLE FOR PRE-PLANNED MAINTENANCE
"This is a non-emergency notification. At approximately 11:00 EST on December 13, 2012, the Seismic Monitoring System was declared inoperable for pre-planned preventative maintenance, MPT-10240 Triaxial Time History Accelerograph. The preventive maintenance is expected to last approximately 5 to 6 hours.
"The Seismic Monitoring System is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification in the Harris Nuclear Plant Emergency Plan. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. This condition does not affect the health of safety of the public or the operation of the facility.
"Licensee has available redundant seismic indication and the on-site Emergency Response Organization has been notified.
"The NRC Resident Inspectors have been notified." |
| Power Reactor | Event Number: 48590 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MATTHEW BUSCH
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/13/2012
Notification Time: 18:36 [ET]
Event Date: 12/13/2012
Event Time: 16:30 [EST]
Last Update Date: 12/14/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
DANIEL HOLODY (R1DO)
LOUISE LUND (NRR)
|
| 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 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO PRIMARY CONTAINMENT SYSTEM DECLARED INOPERABLE
"An increased usage of Nitrogen to maintain Primary Containment pressure within specification was noticed during steady state operation. Investigation into the extra Nitrogen usage revealed that Primary Containment Leakage was in excess of that allowed per Technical Specification 3.3.3.a. No action statement is provided for leakage in excess of Technical Specification 3.3.3.a; therefore in accordance with Technical Specification 3.0.1, the reactor shall be placed in an operational condition in which the specification is not applicable. This requires the plant to be shutdown and cooled down to less than 216 degrees F.
"Additionally, this is reportable as an event or condition that could have prevented fulfillment of a safety function of a system needed to control the release of radioactive material.
"The primary containment was declared inoperable at 1630 EST and a normal orderly plant shutdown was commenced at 1645 EST and will be less than 215 degrees F within 10 hours.
"Investigation of containment leakage is in progress.
"An update will be provided when the plant is in an operational condition in which Technical Specification 3.3.3.a is not applicable."
The licensee has notified the NRC Resident Inspector. Licensee has notified the State of New York.
* * * UPDATE AT 0011 EST ON 12/14/12 FROM CHRISTOPHER GRAPES TO BILL HUFFMAN * * *
"As of 2333 EST on 12/13/2012, the reactor is below 215 degrees F, and containment is no longer required to be operable by Technical Specification 3.3.3. As part of the shutdown, a manual reactor scram was initiated as part of the pre-planned shutdown sequence and the High Pressure Coolant Injection (HPCI) System automatically initiated as expected. At Nine Mile Point Unit 1, a HPCI System actuation signal on low Reactor Pressure Vessel (RPV) level is normally received following a reactor scram, due to level shrink.
"HPCI is a flow control mode of the normal feedwater systems and is not an Emergency Core Cooling System. At 1913 EST, RPV level was restored above the HPCI system low level actuation set point and the HPCI system initiation signal was reset. Pressure control was established on the turbine bypass valves, the preferred system. No Electromatic Relief Valves actuated due to the scram.
"Nine Mile Point Unit 1 is currently in Cold Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via shutdown cooling (SDC). The offsite grid is stable with no grid restrictions or warnings in effect."
The licensee has notified the NRC Resident Inspector and State authorities. Notified R1DO (Holody) and NRR EO (Lund). | |