Event Notification Report for November 23, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/22/2008 - 11/23/2008
Power Reactor
Event Number: 44680
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM BAKER
HQ OPS Officer: PETE SNYDER
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM BAKER
HQ OPS Officer: PETE SNYDER
Notification Date: 11/23/2008
Notification Time: 18:13 [ET]
Event Date: 11/23/2008
Event Time: 12:00 [CST]
Last Update Date: 11/23/2008
Notification Time: 18:13 [ET]
Event Date: 11/23/2008
Event Time: 12:00 [CST]
Last Update Date: 11/23/2008
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):
EUGENE GUTHRIE (R2)
EUGENE GUTHRIE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
PRESSURE BOUNDARY LEAK
"During performance of Unit 1 vessel leak test in accordance with 1-SI-3.3.1.A - ASME Section XI System Leakage Test of the Reactor Pressure Vessel and Associated Piping, a pressure boundary leak was discovered on an instrument line connected to the reactor pressure vessel. This instrument line is a ASME Code Class 1 equivalent component (nozzle safe end) on pressure vessel nozzle N11B and connecting upstream of primary containment penetration X-29B. This caused entry into Technical Requirements Manual (TRM) 3.4.3 - Structural Integrity - Condition A - in which the applicability is at all times and the required action is to immediately restore the structural integrity of the affected component to within its limit or maintain the reactor in MODE 4 or 5 or the reactor coolant system less than 50?F above the minimum temperature required by NDT considerations, until each indication of a defect has been investigated and evaluated. The plant is currently in MODE 4.
"This event is reportable within 8 hours under 10CFR50.72 (b)(3)(ii)(A) Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. This event is also a reportable within 60 days under 10CFR50.73(a)(2)(ii)(A) any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. The NRC Resident Inspector has been notified. This condition has been documented in the BFN Corrective Action program as PER# 157918.
"Unit 2 and 3 remain at 100% power and are not affected by this event."
"During performance of Unit 1 vessel leak test in accordance with 1-SI-3.3.1.A - ASME Section XI System Leakage Test of the Reactor Pressure Vessel and Associated Piping, a pressure boundary leak was discovered on an instrument line connected to the reactor pressure vessel. This instrument line is a ASME Code Class 1 equivalent component (nozzle safe end) on pressure vessel nozzle N11B and connecting upstream of primary containment penetration X-29B. This caused entry into Technical Requirements Manual (TRM) 3.4.3 - Structural Integrity - Condition A - in which the applicability is at all times and the required action is to immediately restore the structural integrity of the affected component to within its limit or maintain the reactor in MODE 4 or 5 or the reactor coolant system less than 50?F above the minimum temperature required by NDT considerations, until each indication of a defect has been investigated and evaluated. The plant is currently in MODE 4.
"This event is reportable within 8 hours under 10CFR50.72 (b)(3)(ii)(A) Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. This event is also a reportable within 60 days under 10CFR50.73(a)(2)(ii)(A) any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. The NRC Resident Inspector has been notified. This condition has been documented in the BFN Corrective Action program as PER# 157918.
"Unit 2 and 3 remain at 100% power and are not affected by this event."
General Information or Other
Event Number: 44681
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: GILES ENGINEERING
Region: 4
City: DALLAS State: TX
County:
License #: 4919
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: JOE O'HARA
Licensee: GILES ENGINEERING
Region: 4
City: DALLAS State: TX
County:
License #: 4919
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: JOE O'HARA
Notification Date: 11/24/2008
Notification Time: 13:20 [ET]
Event Date: 11/23/2008
Event Time: 16:00 [CST]
Last Update Date: 11/24/2008
Notification Time: 13:20 [ET]
Event Date: 11/23/2008
Event Time: 16:00 [CST]
Last Update Date: 11/24/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CLAUDE JOHNSON (R4)
LANCE ENGLISH (ILTA)
MEXICO VIA E-MAIL
MICHELE BURGESS (FSME)
CLAUDE JOHNSON (R4)
LANCE ENGLISH (ILTA)
MEXICO VIA E-MAIL
MICHELE BURGESS (FSME)
STOLEN TROXLER MOISTURE DENSITY GAUGE
"While at the office, Site002, on Sunday, November 23, 2008, the licensee had a truck with a gauge secured in the bed which was stolen by cutting the chain and lock. The employees had left to go to a jobsite and upon returning to the office noticed that the gauge had been stolen. The Dallas Police Department was notified and a report was filed. The Agency was notified at the start of business on Monday, November 24, 2008. The gauge was a Troxler 3430 (S/N 334330) and had two sources, 8mCi of Cs-137 (S/N 750-8953) and 40mCi of Am-241 (S/N 471455)."
TX Incident #- I-8582
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.
"While at the office, Site002, on Sunday, November 23, 2008, the licensee had a truck with a gauge secured in the bed which was stolen by cutting the chain and lock. The employees had left to go to a jobsite and upon returning to the office noticed that the gauge had been stolen. The Dallas Police Department was notified and a report was filed. The Agency was notified at the start of business on Monday, November 24, 2008. The gauge was a Troxler 3430 (S/N 334330) and had two sources, 8mCi of Cs-137 (S/N 750-8953) and 40mCi of Am-241 (S/N 471455)."
TX Incident #- I-8582
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.