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Event Notification Report for February 2, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/01/2007 - 02/02/2007

** EVENT NUMBERS **


43129 43130 43132 43135 43136 43137 43138

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General Information or Other Event Number: 43129
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: AQUATERRA ENGINEERING
Region: 4
City: RIDGELAND State: MS
County: MADISON
License #: MS-724-01
Agreement: Y
Docket:
NRC Notified By: BOBBY SMITH
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/29/2007
Notification Time: 12:31 [ET]
Event Date: 01/26/2007
Event Time: 12:00 [CST]
Last Update Date: 01/29/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CLAUDE JOHNSON (R4)
GREG MORELL (NMSS)
ILTAB (e-mailed)) ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

MISSISSIPPI AGREEMENT STATE REPORT - STOLEN TROXLER DENSITY GAUGE

Following Agreement State Report was received via e-mail

"Description of Incident: DRH received notification on 1-28-07 from Mississippi Emergency Management Agency (MEMA) about a Troxler Model 3411 M/D gauge, Serial # 9533, that had been reported stolen. The gauge belonged to Aquaterra Engineering. The RSO was contacted and he stated that the gauge had been locked in a tool box. The tool box was not big enough to put the shipping container in it also, so the shipping container was in the bed of the truck. The RSO stated that the lock was cut on the tool box allowing the gauge to be removed. He also stated that the gauge's source rod was locked. Issued press release on 1-29-07.

"Date of Incident: Sometime between 1-26-07 and 1-28-07

"Isotope(s): Cesium-137, 8 millicuries; & Americium-241:Be, 40 millicuries.

"Describe clean-up actions taken by DRH: None required.

"List any other actions required of DRH: Licensee will be required to send a written report of stolen gauge within 30 days.

"List any actions taken to notify NRC, other Agreement States: Notified Meridian, MS, Police Department. Notified Lauderdale County Emergency Management. Notified NRC by E-mail. Notified Alabama Radiation Control by phone. Mississippi Department of Health issued press release.

"Case Closed: No

"Record of incident in RAM files: Yes

"Enforcement action taken: Investigation ongoing."

Incident No. MS 07001


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.

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General Information or Other Event Number: 43130
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: MRM CONSTRUCTION SERVICES
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ 7-512
Agreement: Y
Docket:
NRC Notified By: AUBREY V. GODWIN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/29/2007
Notification Time: 17:05 [ET]
Event Date: 01/29/2007
Event Time: 04:00 [MST]
Last Update Date: 01/29/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CLAUDE JOHNSON (R4)
GARY JANOSKO (NMSS)
ILTAB (e-mail) ()
MEXICO (E-mailed) ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

ARIZONA AGREEMENT STATE REPORT - STOLEN CPN DENSITY GAUGE

Following Agreement State Report was received via facsimile

"At approximately 9:00 AM January 29, 2007, the Agency was informed that the Licensee had a Nuclear Density Gauge stolen from the back of a pickup truck, while the user was at his residence. The missing gauge is a CPN Model MC-3 gauge, SN 8853. The theft occurred between 4 - 6:15 AM on January 29, 2007. The gauge contains 8 mCi (millicuries) of Cesium-137 and 40 mCi (millicuries) Am:Be-241.

"The Phoenix PD is investigating and issued report number 2007-701-92664.

"The Licensee is offering a $500.00 reward for the recovery of the source. A press release is to be made by the licensee.

"The Agency continues to investigate.

"First Notice: 07-001"

The states of CA, NV, CO, UT , NM, and U.S. NRC , FBI and Mexico 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.

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Power Reactor Event Number: 43132
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BERNIE LITKETT
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/30/2007
Notification Time: 00:49 [ET]
Event Date: 01/29/2007
Event Time: 23:10 [EST]
Last Update Date: 02/01/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
CHRISTOPHER CAHILL (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 22 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM ON LOW REACTOR PRESSURE VESSEL (RPV) WATER LEVEL

"On 1/29/07 with Hope Creek reactor startup in progress, in mode 1 at 22% Reactor power, Secondary Condensate Pump Minimum Flow Control Valves began to cycle. Reactor water level reached 39" (RPV level 7) and then lowered to 30" (RPV level 4). Manual control of the Reactor Feed pumps was taken, however, RPV water level continued to lower to 15" (Reactor scram on RPV water level is 12.5") at which time the reactor mode switch was locked in shutdown. There were no ECCS injections and all ECCS systems are operable. Initial review of the event indicates that all systems operated as expected with the exception of the Secondary Condensate pump minimum flow valves and the 'A' IRM failed to insert. Current plant conditions as of 1/30/07 at 0010 are: Hope Creek is in mode 3 at 565 psig. The Main Steam Line Isolation valves are open. 'B' and 'C' Primary Condensate Pumps, 'B' and 'C' Secondary Condensate Pumps, and 'A' Rx Feed Pump are feeding the vessel. All control rods have fully inserted on the scram and Main Turbine Bypass valves are removing decay heat."

The licensee will inform the LAC (Lower Alloways Creek Township) and has informed the NRC Resident Inspector.

* * * UPDATE FROM REED TO HUFFMAN AT 1719 EST ON 2/01/07 * * *

"Based on the post-trip review performed by the licensee, it was determined that the in-service Reactor Feed Pump Minimum Flow Recirculation Valve opened in response to the feed flow adjustments. Reactor vessel level reached the low-level trip set point and an automatic reactor scram occurred. During the event analysis it was determined that the operator initiated the manual scram two seconds after the automatic low level scram occurred. A post event equipment performance review concluded that the Secondary Condensate Pump Minimum Flow Recirculation Valves operated as expected."

The licensee notified the NRC Resident Inspector. The R1DO (Cahill) notified.

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General Information or Other Event Number: 43135
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: FLORIDA INTERNATIONAL UNIVERSITY
Region: 1
City: MIAMI State: FL
County:
License #: 3669-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/30/2007
Notification Time: 16:12 [ET]
Event Date: 02/01/2006
Event Time: 12:00 [EST]
Last Update Date: 01/30/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1)
LAWRENCE KOKAJKO (NMSS)
ILTAB (e-mailed) ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

FLORIDA AGREEMENT STATE REPORT - LOSS GAS CHROMATOGRAPH

Following Agreement State Report was received via e-mail

"Licensee reported loss of gauge. Last seen during 2/06 inventory. Roof over storage area was replaced in 03/06 and all instruments/equipment had to be moved. Repairs were complete in 5/06. The gauge was noted missing in 8/06 inventory. Licensee reports an extensive search was conducted for several months. The loss was reported to this office 1/30/07. Licensee will submit a written report. Florida is investigating."


Device Type: Gas Chromatograph
Manufacturer: Hewlett-Packard
Model Number: 5890
Serial Number: SN L4479
Isotope(s): Ni-63
Activity: 15.8 millicuries in 1988 (13.2 millicuries now)
Material Form: Sealed Source
Incident Category: Loss of Control - Lost, Abandoned, or Stolen Materials
Location Classification: Controlled Area

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.

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Power Reactor Event Number: 43136
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES HUTTO
HQ OPS Officer: BILL GOTT
Notification Date: 02/01/2007
Notification Time: 00:36 [ET]
Event Date: 01/31/2007
Event Time: 18:45 [CST]
Last Update Date: 02/01/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
MIKE ERNSTES (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

POTENTIAL FOR PENETRATION RECIRCULATION FILTRATION SYSTEM OVERLOAD

"Due to a procedure based line-up of the Penetration Recirculation Filtration (PRF) system, it has been discovered that the system is placed in a configuration that could prevent it from performing its safety function. The PRF System filters airborne radioactive particulates from the area of the fuel pool following a fuel handling accident or ECCS pump rooms and penetration area of the Auxiliary Building following a loss of coolant accident (LOCA). The PRF system is a standby system that upon a receipt of an actuating Engineering Safety Feature Actuation System signal or upon receipt of a high radiation signal or a low air flow signal from the normal spent fuel pool room ventilation system will start the PRF fans and discharge the ventilation air stream through the system's filters.

"The standard operating procedure for the PRF system directs the control room staff to place the system in a 'full recirculation' mode of operation following a design bases LOCA if the system can maintain a proper vacuum inside the PRF boundary. The 'full recirculation' mode of operation isolates the Recirculation fan discharge to the atmosphere and fully opens the Recirculation fan recirculation damper. This mode of operation is only an additional defense in depth measure and is not credited in the accident analysis. In this mode of operation, it has been discovered that a degraded PRF boundary which allows in leakage into the boundary which is less than the maximum allowable operational limits, could place the system in a configuration that might cause the Exhaust fan to trip. The trip is caused by an overload condition at the supply breaker due to the increased flow of the Exhaust fan to the atmosphere. With the Recirculation fan discharge isolated to the atmosphere and the Exhaust fan inoperable, the PRF system may not establish an adequate vacuum in the PRF boundary during a Post LOCA accident, thus not meeting its design function.

"This condition was discovered on Unit 1, A train PRF system. Since the systems are similar between Units 1 and 2, and the procedure guidance is exactly the same for the 'full recirculation' mode of operation, this condition has the potential to affect both units, both trains of PRF.

"Corrective actions have been completed to eliminate this mode of operation from the procedure guidance given to the control room staff for operation. A major contributor to the in leakage into the PRF boundary on Unit 1 has also been repaired which reduced the running load on the Exhaust fan for that train. With the procedure guidance removed, the system should not be placed in a 'full recirculation' mode of operation, thus eliminating the potential for a failure of the designed safety function of the system."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 43137
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE DEBOARD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/01/2007
Notification Time: 12:18 [ET]
Event Date: 02/01/2007
Event Time: 09:25 [CST]
Last Update Date: 02/01/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID HILLS (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF OFFSITE PHONE CONNECTIONS

At approximately 0925 CST, Braidwood lost approximately 85% of phone functionality. The loss of phones has been determined to be an off site issue and the local phone company is investigating the situation. The Emergency Response Organization (ERO) can still activate ERO pagers using cell phones. The Shift Manager has a dedicated cell phone.

The licensee notified the NRC Resident Inspector.

* * * UPDATE BY KLEVORN TO HUFFMAN AT 2239 EST ON 2/1/07 * * *

The licensee declared the ENS and commercial lines operable based on testing and information from the telephone company. The R3DO (Hills) has been notified.

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Power Reactor Event Number: 43138
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BOB MURELL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/01/2007
Notification Time: 13:20 [ET]
Event Date: 02/01/2007
Event Time: 08:40 [CST]
Last Update Date: 02/01/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DAVID HILLS (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 94 Power Operation 94 Power Operation

Event Text

CONTROLLED SUBSTANCE FOUND IN PROTECTED AREA

Pursuant of 10CFR26.73(b), the following 24 hour notification of a significant fitness for duty event as described in 10CFR26.73(a)(i):

"On 2/01/07 at approximately 0840 CST, off-site testing of a substance proved positive for a controlled substance. The substance was found by a member of plant staff on the plant grounds within the protected area. The plant staff member took possession of the substance and immediately contacted Security staff personnel for assistance. There were no personnel noted in the immediate area of the substance [at the time of discovery]. After confirming the substance, it was turned over to Linn County Sheriff's Department."

The licensee notified the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details.

* * *UPDATE FROM SCHWERTFEJER TO HUFFMAN AT 1948 EST ON 2/1/06 * * *

The licensee has brought drug dog teams onto the site to assist in locating any other controlled substances that may be present. Contact the Headquarters Operations Officer for additional information. R3DO (Hills) and ILTAB (Hahn) informed.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012