Event Notification Report for January 29, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/28/2007 - 01/29/2007
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
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: 03/02/2007
Notification Time: 17:05 [ET]
Event Date: 01/29/2007
Event Time: 04:00 [MST]
Last Update Date: 03/02/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CLAUDE JOHNSON (R4)
GARY JANOSKO (NMSS)
ILTAB (e-mail)
MEXICO (E-mailed)
CLAUDE JOHNSON (R4)
GARY JANOSKO (NMSS)
ILTAB (e-mail)
MEXICO (E-mailed)
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.
* * * UPDATE PROVIDED BY GODWIN TO KOZAL ON 03/2/07 AT 1303 VIA FACSIMILE * * *
"On February 29, 2007, MRM notified this Agency that at 3:15 that afternoon, MRM had received a phone call from a private citizen that some person had tried to sell the gauge to them. The gauge was retrieved in good working condition by the licensee. Local authorities were notified by the licensee."
Notified R4DO (Powers), FSME EO (Wastler) and Mexico (via e-mail).
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.
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.
* * * UPDATE PROVIDED BY GODWIN TO KOZAL ON 03/2/07 AT 1303 VIA FACSIMILE * * *
"On February 29, 2007, MRM notified this Agency that at 3:15 that afternoon, MRM had received a phone call from a private citizen that some person had tried to sell the gauge to them. The gauge was retrieved in good working condition by the licensee. Local authorities were notified by the licensee."
Notified R4DO (Powers), FSME EO (Wastler) and Mexico (via e-mail).
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.
Power Reactor
Event Number: 43131
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RON STOPKA
HQ OPS Officer: JASON KOZAL
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RON STOPKA
HQ OPS Officer: JASON KOZAL
Notification Date: 01/29/2007
Notification Time: 17:33 [ET]
Event Date: 01/29/2007
Event Time: 11:30 [CST]
Last Update Date: 01/29/2007
Notification Time: 17:33 [ET]
Event Date: 01/29/2007
Event Time: 11:30 [CST]
Last Update Date: 01/29/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DAVID HILLS (R3)
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 |
LICENSED EMPLOYEE FAILS FITNESS-FOR-DUTY TEST
"A licensed operator employee had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."
The licensee notified the NRC Resident Inspector.
"A licensed operator employee had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."
The licensee notified the NRC Resident Inspector.
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
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
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
CHRISTOPHER CAHILL (R1)
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 |
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.
"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.