| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/13/2006 - 01/16/2006 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42152 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: SCOTT CIESLEWICZ
HQ OPS Officer: PETE SNYDER | Notification Date: 11/17/2005
Notification Time: 20:53 [ET]
Event Date: 11/17/2005
Event Time: 16:51 [CST]
Last Update Date: 01/13/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
ANN MARIE STONE (R3)
|
| 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 BOTH TRAINS OF SHIELD BUILDING VENTILATION DECLARED INOPERABLE DUE TO MISSING CLAMPS
"At 1651 on 11/17/2005 both trains of Shield Building Ventilation were declared out-of-service because it was identified that Shield Building penetrations 31 and 36NW flexible boot seals were not clamped per the design drawing. Since there is no documentation to show that Shield Building Ventilation would be able to perform its function during a design basis event with no clamps installed, Shield Building Vent was declared inoperable. Clamps have been installed and the penetrations were returned to the design configuration. At 1810 CST Shield Building Ventilation was declared Operable."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM MALONEY TO HUFFMAN AT 1105 EST ON 1/13/06 * * *
The licensee has performed an engineering review and determined that the boot seals would have been capable of performing their design basis function without the clamps installed. Consequently, this event is no longer considered reportable and is being retracted.
The NRC Resident Inspector has been notified by the licensee. R3DO (O'Brien) has also been notified. |
| Power Reactor | Event Number: 42257 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: JOHN KNOKE | Notification Date: 01/13/2006
Notification Time: 16:53 [ET]
Event Date: 01/13/2006
Event Time: 08:30 [CST]
Last Update Date: 01/13/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
REBECCA NEASE (R4)
|
| 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 PRESSURIZER PORV STROKE TIMES EXCEED ANALYSIS ASSUMPTIONS
"The analyses for the Callaway Cold Overpressure Mitigating System (COMS) assumes an opening time and delay time for the pressurizer Power Operated Relief Valves (PORV)s. Evaluations performed by Callaway engineering personnel have determined that PORV stroke times measured during surveillance testing do not account for all of the delay times credited in the Design Bases COMS Analyses of Record. Further reviews determined the allowed delay times could not be met by the control loop. This results in potentially non-conservative PORV lifts settings relative to those specified in the PTLR for satisfying Technical Specification (TS) 3.4.1.2.a and 3.4.12.c.
"At the time the determination was made, the plant was in Mode 1. Technical Specification 3.4.12, COMS, is applicable in Mode 4 with RCS temperature less than or equal to 275 F, Mode 5 and Mode 6 with the head on the reactor vessel. The TS allows other methods of providing cold overpressure protection (ex. Residual Heat Removal system suction relief valves).
"Remedial actions have been initiated to ensure the COMS TS function is maintained when required, pending completion of corrective actions."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42258 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TOM CHALMERS
HQ OPS Officer: JOHN KNOKE | Notification Date: 01/13/2006
Notification Time: 20:25 [ET]
Event Date: 01/13/2006
Event Time: 16:45 [CST]
Last Update Date: 01/13/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KENNETH O'BRIEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 95 | Power Operation | 95 | Power Operation | Event Text LOSS OF COMMUNICATIONS - GREATER THAN 25% OF EMERGENCY NOTIFICATION SIRENS UNAVAILABLE
"At 1645 on 01/13/2006, greater than 25% of the Clinton Power Station emergency notification sirens became unavailable, most likely caused by inclement weather. A total of 18 of the 44 sirens were unavailable.
"At 1745, 15 of the 18 inoperable sirens were restored to an operable status. 1(one) siren remains unavailable due to a loss of communication and two others due to loss of power.
"At 1745, this condition was considered to be a major loss of emergency preparedness. Restoration of the 3 remaining unavailable sirens is in progress. Appropriate compensatory measures are in place for the 3 remaining unavailable sirens."
The licensee notified the local DeWitt County Sheriff office and the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 42259 | Rep Org: VIGO COAL COMPANY
Licensee: VIGO COAL COMPANY
Region: 3
City: BOONEVILLE State: IN
County:
License #: 13-32559-01
Agreement: N
Docket:
NRC Notified By: JOHN HARMAN
HQ OPS Officer: JOHN MacKINNON | Notification Date: 01/14/2006
Notification Time: 11:44 [ET]
Event Date: 01/11/2006
Event Time: [CST]
Last Update Date: 01/14/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
KENNETH O'BRIEN (R3)
C.W. (BILL) REAMER (NMSS)
| Event Text COAL ANALYZER SHUTTER INSTALLED INCORRECTLY
Last Wednesday, 01/11/06, an NRC Inspector discovered that the company's SABIA online, Model No. XC-5000 coal analyzer which contains a Cs-137 source could not lock the shutter closed. The online analyzer is used for elemental analysis of coal. Vigo Coal contacted SABI, located in CA and their representatives arrived at Vigo Coal Company this morning, 01/14/06.
The SABIA representative found that the lever arm to the shutter of the camera was installed 180 degrees out of its proper position (reversed). The SABIA representative took the two screws out and reversed the handle, which corrected the problems. The shutter worked properly. The holes on the lever and the camera shutter now line up so a padlock can be installed to lock the camera shut.
There were no personnel exposures, contamination nor safety issues associated with this incident. |
| Power Reactor | Event Number: 42260 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEVIN O'SHEA
HQ OPS Officer: JOHN KNOKE | Notification Date: 01/15/2006
Notification Time: 12:36 [ET]
Event Date: 01/15/2006
Event Time: 11:04 [CST]
Last Update Date: 01/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
KENNETH O'BRIEN (R3)
MICHAEL MAYFIELD (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 85 | Power Operation | 85 | Power Operation | Event Text TS SHUTDOWN DUE TO ELECTROMATIC RELIEF VALVES (ERVS) DECLARED INOPERABLE
"At 1014 hours on January 15, 2006, the four Unit 1 Electromatic Relief Valves (ERVs) were declared inoperable due to concerns related to the ERV actuators. These operability concerns originated from inspections and testing performed on the Unit 2 ERVs which indicate evidence of mechanical interference issues that could prevent proper ERV operation (note that Unit 2 was shutdown on January 14, 2006 to perform ERV actuator inspections). In accordance with Technical Specification 3.4.3, Condition B, 3.5.1 Condition H, and 3.6.1.6 Condition B, Unit 1 commenced a shutdown on January 15, 2006 at 1104 hours.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(i) as commencement of any nuclear plant shutdown required by the plant's Technical Specifications.
"During the upcoming Unit 1 outage, actuator inspections and ERV testing is planned to confirm the operational ability of the ERVs. Note that the Unit 1 Target Rock Relief Valve and the Main Steam Safety Valves are operable and available to support reactor overpressure protection."
The plant is conducting a normal shutdown per Tech Spec requirements. At 16:00 CST the unit will going off line and by 24:00 CST the plant is expected to be in Mode 4 (Cold Shutdown).
The licensee notified the NRC Resident Inspector. | |