Event Notification Report for February 19, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/18/2007 - 02/19/2007
EVENT NUMBERS
43172431734317043171
Power Reactor
Event Number: 43172
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: JEFF ROTTON
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/19/2007
Notification Time: 15:34 [ET]
Event Date: 02/19/2007
Event Time: 00:00 [CST]
Last Update Date: 02/21/2007
Notification Time: 15:34 [ET]
Event Date: 02/19/2007
Event Time: 00:00 [CST]
Last Update Date: 02/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
MARK RING (R3)
MARK RING (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
DEGRADED CONDITION - 30% THROUGH WALL INDICATION ON REACTOR RECIRC NOZZLE
"Information from a Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) indicates that a linear indication approximately 7" long (centered at the bottom of the weld) and approximately 30% through wall extent (ID connected) exists. The Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) was performed as part of scheduled outage activities.
"TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping.
"This event is reportable under § 50.72(b)(3)(ii), 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded', when there are welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, IWB-3600, 'Analytical Evaluation of Flaws' or ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.'"
The licensee informed the NRC Resident Inspector.
* * * UPDATE PROVIDED BY HANS OLSON TO JEFF ROTTON AT 2315 EST ON 02/21/07 * * *
"Information from a Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) indicates that a linear indication approximately 10" long and approximately 82% through wall extent (Inner Diameter connected) exists. The Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) was performed as part of a follow-up activity for an extent of condition evaluation on RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld).
"TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping."
Corrected error in original report due to event entry error that identified the affected nozzle as RRF-17002 vice the correct identification of RRF-F002
The licensee notified the NRC Resident Inspector. Notified R3DO (Burgess)
"Information from a Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) indicates that a linear indication approximately 7" long (centered at the bottom of the weld) and approximately 30% through wall extent (ID connected) exists. The Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) was performed as part of scheduled outage activities.
"TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping.
"This event is reportable under § 50.72(b)(3)(ii), 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded', when there are welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, IWB-3600, 'Analytical Evaluation of Flaws' or ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.'"
The licensee informed the NRC Resident Inspector.
* * * UPDATE PROVIDED BY HANS OLSON TO JEFF ROTTON AT 2315 EST ON 02/21/07 * * *
"Information from a Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) indicates that a linear indication approximately 10" long and approximately 82% through wall extent (Inner Diameter connected) exists. The Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) was performed as part of a follow-up activity for an extent of condition evaluation on RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld).
"TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping."
Corrected error in original report due to event entry error that identified the affected nozzle as RRF-17002 vice the correct identification of RRF-F002
The licensee notified the NRC Resident Inspector. Notified R3DO (Burgess)
Power Reactor
Event Number: 43173
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: TIM GAFFNEY
HQ OPS Officer: STEVE SANDIN
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: TIM GAFFNEY
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/19/2007
Notification Time: 19:14 [ET]
Event Date: 02/19/2007
Event Time: 14:57 [MST]
Last Update Date: 02/19/2007
Notification Time: 19:14 [ET]
Event Date: 02/19/2007
Event Time: 14:57 [MST]
Last Update Date: 02/19/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
ANTHONY GODY (R4)
ANTHONY GODY (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNIT 2 PERFORMED A TS REQUIRED SHUTDOWN
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On 02/19/2007 at approximately 14:57 hours Mountain Standard Time (MST), Palo Verde Nuclear Generating Station (PVNGS) Unit 2 initiated a plant shutdown as required by Condition 'C' of Technical Specification (TS) LCO 3.5.3 to be in Mode 3 with Pressurizer pressure < 1837 psia and Reactor Coolant System (RCS) Tc < 485 degrees F.
"Limiting Condition for Operability (LCO) 3.5.3 requires that two ECCS trains be Operable. High Pressure Safety Injection Pump (HPSI) 2A was declared inoperable on 02/16/2007 at 13:01 MST and was not restored to Operable status within the TS 72 hour Completion Time due to pump bearing oil leakage exceeding the allowable leakage limit. Efforts are in progress to correct the oil leakage issue.
"The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public."
The observed pump bearing oil leakage is approximately 3 drops/hr. Unit 2 completed a normal reactor shutdown with a manual reactor trip at 20% power. All rods fully inserted. Decay heat is currently being removed via the Main Condenser.
The licensee informed the NRC Resident Inspector.
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On 02/19/2007 at approximately 14:57 hours Mountain Standard Time (MST), Palo Verde Nuclear Generating Station (PVNGS) Unit 2 initiated a plant shutdown as required by Condition 'C' of Technical Specification (TS) LCO 3.5.3 to be in Mode 3 with Pressurizer pressure < 1837 psia and Reactor Coolant System (RCS) Tc < 485 degrees F.
"Limiting Condition for Operability (LCO) 3.5.3 requires that two ECCS trains be Operable. High Pressure Safety Injection Pump (HPSI) 2A was declared inoperable on 02/16/2007 at 13:01 MST and was not restored to Operable status within the TS 72 hour Completion Time due to pump bearing oil leakage exceeding the allowable leakage limit. Efforts are in progress to correct the oil leakage issue.
"The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public."
The observed pump bearing oil leakage is approximately 3 drops/hr. Unit 2 completed a normal reactor shutdown with a manual reactor trip at 20% power. All rods fully inserted. Decay heat is currently being removed via the Main Condenser.
The licensee informed the NRC Resident Inspector.
General Information or Other
Event Number: 43170
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: MATERIALS TESTING OF ARKANSAS
Region: 4
City: LITTLE ROCK State: AR
County:
License #: ARK-859
Agreement: Y
Docket:
NRC Notified By: BERNIE BEVILL
HQ OPS Officer: JOE O'HARA
Licensee: MATERIALS TESTING OF ARKANSAS
Region: 4
City: LITTLE ROCK State: AR
County:
License #: ARK-859
Agreement: Y
Docket:
NRC Notified By: BERNIE BEVILL
HQ OPS Officer: JOE O'HARA
Notification Date: 02/19/2007
Notification Time: 08:56 [ET]
Event Date: 02/19/2007
Event Time: 00:00 [CST]
Last Update Date: 05/21/2007
Notification Time: 08:56 [ET]
Event Date: 02/19/2007
Event Time: 00:00 [CST]
Last Update Date: 05/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANTHONY GODY (R4)
SCOTT MOORE (FSME)
R. WARREN ILTAB
ANTHONY GODY (R4)
SCOTT MOORE (FSME)
R. WARREN ILTAB
AGREEMENT STATE REPORT INVOLVING STOLEN TROXLER MOISTURE DENSITY GAUGE MODEL 3440
The Arkansas Department of Health reported that one of their licensees, Materials Testing of Arkansas, had a Troxler moisture density gauge stolen from a pickup truck in front of a Wal-Mart in Little Rock, Arkansas between 6:00 a.m. and 6:30 a.m. CST. When the licensee returned to the vehicle, he found that the chain securing the gauge had been cut, and the Troxler and some other personal equipment had been stolen from the back of the vehicle. The Troxler is a Model 3440 S/N 19914 and contains 9 milli Curies of Cs-137 and 44 milli Curies of Am-241. The Little Rock Police Department is investigating the theft under case number 07-18990.
The Arkansas Department of Health is preparing a press release on this event.
*** UPDATE FROM STEVE MACK TO KNOKE AT 15:28 EDT ON 5/21/07 ***
The State provided the following information via facsimile:
"On Friday, May 18, 2007, the moisture density gauge stolen on February 19, 2007, was recovered in a vacant residence in Little Rock, Arkansas. The gauge transport case, as well as, the gauge handle were not locked when found. The gauge appeared to be undamaged and was transported to the licensee's authorized storage facility. Representatives from the Arkansas Radiation Control Program conducted a leak test in the field and the RSO was conducting a leak test for analysis by the licensee's consultant prior to placing the gauge back in service.
"The Department [Arkansas Department of Health] considers this event closed."
Notified R4DO (Johnson), FSME (Burgess), ILTAB (Via Email)
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.
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
The Arkansas Department of Health reported that one of their licensees, Materials Testing of Arkansas, had a Troxler moisture density gauge stolen from a pickup truck in front of a Wal-Mart in Little Rock, Arkansas between 6:00 a.m. and 6:30 a.m. CST. When the licensee returned to the vehicle, he found that the chain securing the gauge had been cut, and the Troxler and some other personal equipment had been stolen from the back of the vehicle. The Troxler is a Model 3440 S/N 19914 and contains 9 milli Curies of Cs-137 and 44 milli Curies of Am-241. The Little Rock Police Department is investigating the theft under case number 07-18990.
The Arkansas Department of Health is preparing a press release on this event.
*** UPDATE FROM STEVE MACK TO KNOKE AT 15:28 EDT ON 5/21/07 ***
The State provided the following information via facsimile:
"On Friday, May 18, 2007, the moisture density gauge stolen on February 19, 2007, was recovered in a vacant residence in Little Rock, Arkansas. The gauge transport case, as well as, the gauge handle were not locked when found. The gauge appeared to be undamaged and was transported to the licensee's authorized storage facility. Representatives from the Arkansas Radiation Control Program conducted a leak test in the field and the RSO was conducting a leak test for analysis by the licensee's consultant prior to placing the gauge back in service.
"The Department [Arkansas Department of Health] considers this event closed."
Notified R4DO (Johnson), FSME (Burgess), ILTAB (Via Email)
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.
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: 43171
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DAVID DUNCAN
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DAVID DUNCAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/19/2007
Notification Time: 10:14 [ET]
Event Date: 02/19/2007
Event Time: 08:00 [EST]
Last Update Date: 02/23/2007
Notification Time: 10:14 [ET]
Event Date: 02/19/2007
Event Time: 08:00 [EST]
Last Update Date: 02/23/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK RING (R3)
MARK RING (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EOF NOT AVAILABLE DURING RENOVATION
"Fermi 2 commenced an upgrade to the Emergency Operations Facility (EOF) on February 19, 2007 at 0800. The upgrade consists of furniture replacement and rearrangement of the seating layout. During this work, some floor panels will be removed for cable routing and accordingly the facility will not be available for emergency use. Fermi is making this notification in accordance with 10 CFR 50.72(b)(3)(xiii). In the event EOF activation is necessary, the Alternate EOF will be utilized. Activation and use of the alternate EOF is included in Fermi's Radiological Emergency Response Preparedness Plan. Fermi will notify the NRC upon completion of this work, which is scheduled for Friday February 23, 2007."
The licensee will notify the NRC Resident Inspector.
*** UPDATE FROM KONRAD TO KNOKE AT 17:55 EDT ON 02/23/07 ***
"This is a follow-up to NRC Event No. 43171. The upgrades to the Emergency Operations Facility (EOF), which caused it to be unavailable for emergency use, have been completed and the EOF is now available for use."
The licensee notified the NRC Resident Inspector.
"Fermi 2 commenced an upgrade to the Emergency Operations Facility (EOF) on February 19, 2007 at 0800. The upgrade consists of furniture replacement and rearrangement of the seating layout. During this work, some floor panels will be removed for cable routing and accordingly the facility will not be available for emergency use. Fermi is making this notification in accordance with 10 CFR 50.72(b)(3)(xiii). In the event EOF activation is necessary, the Alternate EOF will be utilized. Activation and use of the alternate EOF is included in Fermi's Radiological Emergency Response Preparedness Plan. Fermi will notify the NRC upon completion of this work, which is scheduled for Friday February 23, 2007."
The licensee will notify the NRC Resident Inspector.
*** UPDATE FROM KONRAD TO KNOKE AT 17:55 EDT ON 02/23/07 ***
"This is a follow-up to NRC Event No. 43171. The upgrades to the Emergency Operations Facility (EOF), which caused it to be unavailable for emergency use, have been completed and the EOF is now available for use."
The licensee notified the NRC Resident Inspector.