Event Notification Report for August 26, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/25/2005 - 08/26/2005
Power Reactor
Event Number: 41951
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRIAN FERGUSON
HQ OPS Officer: JOHN KNOKE
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRIAN FERGUSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/27/2005
Notification Time: 00:19 [ET]
Event Date: 08/26/2005
Event Time: 18:24 [MST]
Last Update Date: 08/27/2005
Notification Time: 00:19 [ET]
Event Date: 08/26/2005
Event Time: 18:24 [MST]
Last Update Date: 08/27/2005
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):
WILLIAM JONES (R4)
WILLIAM JONES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 1 | Startup | 0 | Hot Standby |
RPS ACTUATION - REACTOR SCRAM ON HIGH STEAM GENERATOR LEVEL
"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 August 26, 2005, at approximately 18:24 Mountain Standard Time (MST) Palo Verde Unit 1 experienced an automatic reactor scram on high steam generator #1 level. All rods inserted, as required. Unit 1 was at normal operating temperature and pressure prior to the trip. The main turbine was not yet synchronized to the grid; turbine chest warming was in progress. The main turbine automatically tripped in response to the reactor trip. A reactor startup had been completed and operators were transferring feedwater from a motor driven auxiliary feedwater pump to the steam driven 'A' main feedwater pump at approximately 1.2% reactor power. Steam generator #1 level decreased from a normal level of approximately 40% narrow range (approx. 77% wide range) to approximately 12% narrow range (approx. 66% wide range). An operator took manual control of feedwater to increase level. Upon returning feedwater control to automatic after level was restored, steam generator #1 level continued to increase, resulting in a reactor trip on high steam generator level at approximately the Technical Specification reactor trip and Main Steam Isolation Signal (MSIS) setpoint of 91.5%. The MSIS (ESF actuation) functioned as required. No other ESF actuations occurred or were required. No emergency classification was required per the Emergency Plan. Safety related buses remained energized during and following the reactor trip. The Emergency Diesel Generators did not start and were not required. The offsite power grid is stable. No LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event that contributed to the event. The maximum power level during the feedwater transient was approximately 8.5%.
"Unit 1 is stable at normal operating temperature and pressure in Mode 3. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The maximum RCS pressure was approximately 2251 psia (normal 2250). The maximum steam generator pressure was approximately 1188 psia (normal 1165). The event did not adversely affect the safe operation of the plant or the health and safety of the public."
The licensee notified 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 August 26, 2005, at approximately 18:24 Mountain Standard Time (MST) Palo Verde Unit 1 experienced an automatic reactor scram on high steam generator #1 level. All rods inserted, as required. Unit 1 was at normal operating temperature and pressure prior to the trip. The main turbine was not yet synchronized to the grid; turbine chest warming was in progress. The main turbine automatically tripped in response to the reactor trip. A reactor startup had been completed and operators were transferring feedwater from a motor driven auxiliary feedwater pump to the steam driven 'A' main feedwater pump at approximately 1.2% reactor power. Steam generator #1 level decreased from a normal level of approximately 40% narrow range (approx. 77% wide range) to approximately 12% narrow range (approx. 66% wide range). An operator took manual control of feedwater to increase level. Upon returning feedwater control to automatic after level was restored, steam generator #1 level continued to increase, resulting in a reactor trip on high steam generator level at approximately the Technical Specification reactor trip and Main Steam Isolation Signal (MSIS) setpoint of 91.5%. The MSIS (ESF actuation) functioned as required. No other ESF actuations occurred or were required. No emergency classification was required per the Emergency Plan. Safety related buses remained energized during and following the reactor trip. The Emergency Diesel Generators did not start and were not required. The offsite power grid is stable. No LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event that contributed to the event. The maximum power level during the feedwater transient was approximately 8.5%.
"Unit 1 is stable at normal operating temperature and pressure in Mode 3. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The maximum RCS pressure was approximately 2251 psia (normal 2250). The maximum steam generator pressure was approximately 1188 psia (normal 1165). The event did not adversely affect the safe operation of the plant or the health and safety of the public."
The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 41949
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: UNKNOWN
Region: 3
City: MADISON State: WI
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: PETE SNYDER
Licensee: UNKNOWN
Region: 3
City: MADISON State: WI
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: PETE SNYDER
Notification Date: 08/26/2005
Notification Time: 13:27 [ET]
Event Date: 08/26/2005
Event Time: 00:00 [CDT]
Last Update Date: 08/26/2005
Notification Time: 13:27 [ET]
Event Date: 08/26/2005
Event Time: 00:00 [CDT]
Last Update Date: 08/26/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
KENNETH O'BRIEN (R3)
E. WILLIAM BRACH (NMSS)
KENNETH O'BRIEN (R3)
E. WILLIAM BRACH (NMSS)
AGREEMENT STATE - TRITIUM EXIT SIGNS FOUND IN RECYCLABLES
The State provided the following information via facsimile:
"Wisconsin Radiation Protection Section [RPS] was contacted by Cascade Asset Management Company on August 25th. Workers at Cascade found several exit signs containing Tritium with a shipment of recyclable material. WI RPS staff were dispatched to investigate. Six intact signs and pieces of other signs were found in a trash barrel. Wipes were taken of the signs and barrel, and are being analyzed for contamination. The signs were placed in bags, sealed and placed in a remote part of the building. An investigation into the origin of the signs is under way."
Wisconsin Event Report ID No.: 30
This is less than the quantity of an IAEA Category 3 source.
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.
For some of these sources, such as moisture density gauges or thickness gauges that are IAEA 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.
The State provided the following information via facsimile:
"Wisconsin Radiation Protection Section [RPS] was contacted by Cascade Asset Management Company on August 25th. Workers at Cascade found several exit signs containing Tritium with a shipment of recyclable material. WI RPS staff were dispatched to investigate. Six intact signs and pieces of other signs were found in a trash barrel. Wipes were taken of the signs and barrel, and are being analyzed for contamination. The signs were placed in bags, sealed and placed in a remote part of the building. An investigation into the origin of the signs is under way."
Wisconsin Event Report ID No.: 30
This is less than the quantity of an IAEA Category 3 source.
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.
For some of these sources, such as moisture density gauges or thickness gauges that are IAEA 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.