| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/31/2011 - 04/01/2011 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 46705 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: MACTEC ENGINEERING & CONSULTING
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ 7-326
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/29/2011
Notification Time: 13:58 [ET]
Event Date: 03/28/2011
Event Time: 14:30 [MST]
Last Update Date: 03/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RYAN LANTZ (R4DO)
PAUL MICHALAK (FSME)
LAURA PEARSON (ILTA)
MEXICO - VIA FAX ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE
The following information was received via fax:
"This First Notice constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received WITHOUT verification or evaluation, and is basically all that is known by the Agency [Arizona Radiation Regulatory Agency] Staff at this time.
"At approximately 1000 MDT, March 28, 2011, the Agency was informed that the Licensee had a Troxler Model 3241-C, SN 1884, asphalt content gauge stolen from the F & F construction trailer at the Casa Grande job site. The theft occurred over the weekend. The gauge was locked with a chain in the construction trailer which was parked in a locked, fenced construction job site. The gauge contains 100 mCi Am-241:Be.
"Casa Grande PD is investigating. The Agency continues to look for the source. The states of CA, NV, CO, UT, and NM and Mexico and U.S. NRC and FBI are being notified of this event."
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Agreement State | Event Number: 46706 | Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: ASTEN JOHNSON
Region: 1
City: CHAPIN State: SC
County:
License #: SC-534
Agreement: Y
Docket:
NRC Notified By: MARK WINDHAM
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/29/2011
Notification Time: 20:02 [ET]
Event Date: 03/29/2011
Event Time: [EDT]
Last Update Date: 03/29/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY POWELL (R1DO)
PAUL MICHALAK (FSME)
LAURA PEARSON (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN NDC DRAIN PROFILE GAUGE
An NDC Model 104-P drainage profile gauge, serial number 1282, was stolen from a licensee vehicle. The box containing the gauge was chained to the floor of the vehicle which was also locked. The gauge contains an 80 mCi Am-241 source. A report was filed with the Chapin, SC police department.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Power Reactor | Event Number: 46714 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOE O'HARA | Notification Date: 03/31/2011
Notification Time: 11:17 [ET]
Event Date: 03/30/2011
Event Time: 14:05 [CDT]
Last Update Date: 03/31/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
RYAN LANTZ (R4DO)
|
| 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 CONTRABAND FOUND INSIDE THE PROTECTED AREA
"While cleaning out portable toilets being used at the site, the waste disposal vendor employee discovered a two ounce (shot sized) liquor bottle in one of the units. The unit had been on-site since 2/25/11 and was staged in the Protected Area. The waste disposal vendor indicated that it is unlikely the bottle was in the portable toilet prior to delivery to the site."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 46715 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MICAH BENNINGFIELD
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/31/2011
Notification Time: 20:50 [ET]
Event Date: 03/31/2011
Event Time: 14:32 [CDT]
Last Update Date: 03/31/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RYAN LANTZ (R4DO)
|
| 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 UNANALYZED CONDITION IDENTIFIED FOR INOPERABLE RWST LEVEL
"In response to a condition identified in late 2010 concerning the control and removal of hazard barriers in the plant, a review of the basis and analysis for high energy line breaks (HELBs) and the barriers for protecting against such events has been underway at Callaway in accordance with the plant's corrective action program. While following up on a question from the NRC Resident Inspector, and as a result of an additional question from the Nuclear Oversight organization at Callaway, it was identified that non-safety piping located in the valve room associated with the Refueling Water Storage Tank (RWST) could potentially [make] all four RWST low water level pressure transmitters inoperable in the event of a malfunction of the non-safety piping concurrent with a design-basis loss-of-coolant accident (LOCA) and/or following a seismic event. The RWST water level transmitters (which are located in the RWST valve room) perform a safety-related function for the emergency core cooling system (ECCS) by automatically swapping suction sources for the ECCS during a LOCA from the RWST to the containment sumps when a low water level condition is reached in the RWST. These instrument channels are required to be OPERABLE in Modes 1, 2, 3 and 4 per Callaway Technical Specification 3.3.2, 'Engineered Safety Feature Actuation System (ESFAS) Instrumentation.'
"The subject non-safety piping delivers steam supplied by the Auxiliary Steam system to (and from) heaters surrounding the RWST for maintaining RWST contents above the minimum required temperature during winter conditions. The piping passes through the RWST valve room containing the noted RWST water level transmitters which were designed only for a mild environment. It has been identified, however, that the non-safety Auxiliary Steam piping constitutes a high energy line and that its failure could create harsh (hot and wet) conditions in the valve room to which the RWST water level instrumentation was not designed.
"Per the Callaway FSAR, where non-safety piping interfaces with safety-related piping or systems, the design must be such that failure of the non-safety piping does not adversely affect the safety function(s) of the interfacing safety-related piping or system (since non-safety piping may be assumed to malfunction in conjunction with a design-basis accident). In this case, and based on a conservative interpretation of the FSAR, if the non-safety piping in the RWST valve room is assumed to malfunction (i.e., break), a failure of the RWST instrumentation could occur, thereby preventing the ECCS suction swap over from occurring as required or assumed for LOCA mitigation.
"This condition required declaring all four RWST water level channels inoperable. In light of recognizing that the RWST water level instruments could be subject to a harsh environment when they were only designed for a mild environment, and could thus fail as a result, this condition represents an unanalyzed condition that significantly degrades plant safety. With regard to the impact on the required ECCS suction swap over function that requires the RWST water level channels to be operable, the inoperability of all four instrument channels is a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to shutdown the reactor and maintain it in a safe condition, remove residual heat, control the release of radioactive material, and mitigate the consequences of an accident.
"Upon declaring the RWST water level instrument channels inoperable, TS Limiting Condition for Operation (LCO) 3.0.3 was entered at time 1432 CDT on 3/31/2011. At 1634 CDT, the Auxiliary Steam system was isolated and depressurized. This removed the energy that could be released from a break in the non-safety piping, thereby restoring Operability for the RWST water level instruments.
"The NRC Senior Resident Inspector was notified." |
| Power Reactor | Event Number: 46716 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/31/2011
Notification Time: 23:32 [ET]
Event Date: 03/31/2011
Event Time: 21:26 [CDT]
Last Update Date: 03/31/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RYAN LANTZ (R4DO)
|
| 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 IDENTIFIED UNSEALED FLOOD BARRIER PENETRATIONS
"During investigations of flood barrier penetrations, two approximately 4 inch conduits have been identified that are not sealed. These conduits penetrate the south wall of the auxiliary building near the transformers into room 19. Flooding through the penetrations could have impacted the ability of the station's auxiliary feedwater (AFW) pumps to perform their design accident mitigation functions.
"This eight-hour notification is being made pursuant to 10 CFR 50.72 (b)(3)(v).
"The penetrations are at an approximate elevation of 1007 [feet]. The river level has been less than 997 feet Mean Sea Level (MSL) since prior to December 1, 2010. The AFW pumps are operable. There are not any indications of conditions that might result in a flood. Actions are in progress to plug the penetrations."
The NRC Resident Inspector has been notified. | |