Event Notification Report for October 15, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/14/2009 - 10/15/2009
EVENT NUMBERS
454424543345434454354543745438
General Information or Other
Event Number: 45442
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THRUBIT LLC
Region: 4
City: HOUSTON State: TX
County:
License #: 06030
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Licensee: THRUBIT LLC
Region: 4
City: HOUSTON State: TX
County:
License #: 06030
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/16/2009
Notification Time: 14:15 [ET]
Event Date: 10/15/2009
Event Time: 00:00 [CDT]
Last Update Date: 10/16/2009
Notification Time: 14:15 [ET]
Event Date: 10/15/2009
Event Time: 00:00 [CDT]
Last Update Date: 10/16/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CHUCK CAIN (R4DO)
MARK DELLIGATTI (FSME)
CHUCK CAIN (R4DO)
MARK DELLIGATTI (FSME)
AGREEMENT STATE REPORT INVOLVING POTENTIAL LOSS OF RADIOACTIVE MATERIAL DURING SHIPMENT
The following information was received from the State of Texas via email:
"On October 16, 2009, at 11:35 AM, the licensee notified the Agency [State of Texas] that a 1.78 curie Cesium (Cs)-137 sources, and a 10.8 millicurie California (Cf) -252 source was lost in transport. The sources were picked up by a common carrier on October 14, 2009, for delivery to their facility in Oklahoma City, Oklahoma. At 1600 on October 15, 2009, the licensee was informed that the sources had not arrived in Oklahoma City. The RSO contacted the shipper and was informed that they believed that the sources had been placed on a truck going to Albuquerque, New Mexico. At about 3:00 AM on October 16, 2009, the licensee was notified that the sources were not on the truck going to Albuquerque. The shipper stated that they would contact all of their facilities (290 of them) to look for the packages. The Cs-137 source is in a container that weighs 320 pounds and labeled as Yellow II with a TI of 0.2. The Cf-252 source is in a container that weighs 185 pounds, is labeled as a Yellow II and a TI of 0.6. The RSO went to the shippers facility in Houston and searched for the packages. He did not find them. The shipper will contact the licensee as soon as the sources are located. The license will provide additional information as it is received."
The State of Oklahoma was informed of the missing shipment.
Texas Incident No.: I-8679
* * * UPDATE AT 1951 EDT ON 10/16/09 FROM ART TUCKER TO S. SANDIN * * *
The following update was received from the State of Texas via email:
"On October 16, 2009, at 1715 CT, the licensee contacted the Agency and informed them that at 1657 CT, the licensee was contacted by the shipping company and informed that the two sources had been located at their facility in Kansas City, Mo. The shipping company will deliver the sources to the licensee's facility in Oklahoma City on October 17, 2009."
Notified R4DO (Cain) and FSME EO (Delligatti).
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
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 following information was received from the State of Texas via email:
"On October 16, 2009, at 11:35 AM, the licensee notified the Agency [State of Texas] that a 1.78 curie Cesium (Cs)-137 sources, and a 10.8 millicurie California (Cf) -252 source was lost in transport. The sources were picked up by a common carrier on October 14, 2009, for delivery to their facility in Oklahoma City, Oklahoma. At 1600 on October 15, 2009, the licensee was informed that the sources had not arrived in Oklahoma City. The RSO contacted the shipper and was informed that they believed that the sources had been placed on a truck going to Albuquerque, New Mexico. At about 3:00 AM on October 16, 2009, the licensee was notified that the sources were not on the truck going to Albuquerque. The shipper stated that they would contact all of their facilities (290 of them) to look for the packages. The Cs-137 source is in a container that weighs 320 pounds and labeled as Yellow II with a TI of 0.2. The Cf-252 source is in a container that weighs 185 pounds, is labeled as a Yellow II and a TI of 0.6. The RSO went to the shippers facility in Houston and searched for the packages. He did not find them. The shipper will contact the licensee as soon as the sources are located. The license will provide additional information as it is received."
The State of Oklahoma was informed of the missing shipment.
Texas Incident No.: I-8679
* * * UPDATE AT 1951 EDT ON 10/16/09 FROM ART TUCKER TO S. SANDIN * * *
The following update was received from the State of Texas via email:
"On October 16, 2009, at 1715 CT, the licensee contacted the Agency and informed them that at 1657 CT, the licensee was contacted by the shipping company and informed that the two sources had been located at their facility in Kansas City, Mo. The shipping company will deliver the sources to the licensee's facility in Oklahoma City on October 17, 2009."
Notified R4DO (Cain) and FSME EO (Delligatti).
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
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: 45433
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: JOHN KNOKE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 10/15/2009
Notification Time: 09:06 [ET]
Event Date: 10/15/2009
Event Time: 05:37 [CDT]
Last Update Date: 10/15/2009
Notification Time: 09:06 [ET]
Event Date: 10/15/2009
Event Time: 05:37 [CDT]
Last Update Date: 10/15/2009
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):
ERIC DUNCAN (R3DO)
ERIC DUNCAN (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 97 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO REACTOR RECIRCULATION PUMP TRIP
"At 0537 hours on October 15, 2009, the 'B' Reactor Recirculation pump tripped. The reactor mode switch was placed in shutdown due to rising reactor water level (approx. 49 inches) prior to the Level 8 automatic scram setpoint (52 inches). All controls rods inserted as a result of the manual scram. All systems performed as expected. Reactor water level is being controlled by the motor driven feedwater pump. Main steam isolation valves were manually closed and decay heat was initially controlled through the main steam line drains to the main condenser via the main turbine bypass valves. Reactor Core Isolation Cooling (RCIC) was manually placed into service (tank-to-tank) to assist in RPV pressure control. RCIC is currently being used for decay heat removal. Investigation is underway to determine the cause of the Reactor Recirculation pump trip."
The licensee will be contacting the state, and issuing a press release.
The NRC Senior Resident Inspector has been notified.
"At 0537 hours on October 15, 2009, the 'B' Reactor Recirculation pump tripped. The reactor mode switch was placed in shutdown due to rising reactor water level (approx. 49 inches) prior to the Level 8 automatic scram setpoint (52 inches). All controls rods inserted as a result of the manual scram. All systems performed as expected. Reactor water level is being controlled by the motor driven feedwater pump. Main steam isolation valves were manually closed and decay heat was initially controlled through the main steam line drains to the main condenser via the main turbine bypass valves. Reactor Core Isolation Cooling (RCIC) was manually placed into service (tank-to-tank) to assist in RPV pressure control. RCIC is currently being used for decay heat removal. Investigation is underway to determine the cause of the Reactor Recirculation pump trip."
The licensee will be contacting the state, and issuing a press release.
The NRC Senior Resident Inspector has been notified.
Power Reactor
Event Number: 45434
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MICHAEL NEMCEK
HQ OPS Officer: STEVE SANDIN
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MICHAEL NEMCEK
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/15/2009
Notification Time: 14:47 [ET]
Event Date: 10/15/2009
Event Time: 12:25 [EDT]
Last Update Date: 10/15/2009
Notification Time: 14:47 [ET]
Event Date: 10/15/2009
Event Time: 12:25 [EDT]
Last Update Date: 10/15/2009
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):
ERIC DUNCAN (R3DO)
ERIC DUNCAN (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 75 | Power Operation |
UNIT COMMENCED SHUTDOWN DUE TO INOPERABLE DIVISION 2 EMERGENCY SERVICE WATER SYSTEM
"This event is being reported in accordance with 10CFR50.72(b)(2)(i). On October 15, 2009, at approximately 1225 hours, the Perry Nuclear Power Plant commenced a Technical Specification required plant shutdown.
"On October 14, 2009, At 1747 hours, the Division 2 Emergency Service Water (ESW) system was declared inoperable and unavailable for planned work. The plant entered Technical Specification (TS) 3.7.1 Action A for one inoperable ESW Division. Other supported TSs were also entered (TS 3.8.1 for the Division 2 diesel generator, TS 3.6.1.7 for Containment Spray 'B', TS 3.6.2.3 for Suppression Pool Cooling 'B', TS 3.7.10 for Emergency Closed Cooling 'B', TS 3.5.1 for LPCI 'B' & 'C', among others).
"On October 15, 2009, at 0601 hours, the ESW 'B' pump was started for a planned pump run. At 0718 hours, the ESW 'B' pump tripped for unknown reasons. The determination was made to commence a controlled plant shutdown and power reduction commenced at 1225 hours. This decision was based on the anticipated investigation and repair time of ESW 'B' pump exceeding the TS 3.7.1 Action A 72 hour LCO completion time, and therefore, Action B requires the plant to be in MODE 3 within 12 hours and in MODE 4 in 36 hours. The TS 3.7.1 Action A 72 hour LCO completion time coincides with October 17, 2009, at 1747 hours.
"Currently, the plant is expected to be in MODE 3 at approximately 2300 hours on October 15, 2009.
"The NRC Resident Inspector has been notified. The State and Counties will also be notified."
"This event is being reported in accordance with 10CFR50.72(b)(2)(i). On October 15, 2009, at approximately 1225 hours, the Perry Nuclear Power Plant commenced a Technical Specification required plant shutdown.
"On October 14, 2009, At 1747 hours, the Division 2 Emergency Service Water (ESW) system was declared inoperable and unavailable for planned work. The plant entered Technical Specification (TS) 3.7.1 Action A for one inoperable ESW Division. Other supported TSs were also entered (TS 3.8.1 for the Division 2 diesel generator, TS 3.6.1.7 for Containment Spray 'B', TS 3.6.2.3 for Suppression Pool Cooling 'B', TS 3.7.10 for Emergency Closed Cooling 'B', TS 3.5.1 for LPCI 'B' & 'C', among others).
"On October 15, 2009, at 0601 hours, the ESW 'B' pump was started for a planned pump run. At 0718 hours, the ESW 'B' pump tripped for unknown reasons. The determination was made to commence a controlled plant shutdown and power reduction commenced at 1225 hours. This decision was based on the anticipated investigation and repair time of ESW 'B' pump exceeding the TS 3.7.1 Action A 72 hour LCO completion time, and therefore, Action B requires the plant to be in MODE 3 within 12 hours and in MODE 4 in 36 hours. The TS 3.7.1 Action A 72 hour LCO completion time coincides with October 17, 2009, at 1747 hours.
"Currently, the plant is expected to be in MODE 3 at approximately 2300 hours on October 15, 2009.
"The NRC Resident Inspector has been notified. The State and Counties will also be notified."
General Information or Other
Event Number: 45435
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: HOTWELL US LTD
Region: 4
City: HOUSTON State: TX
County:
License #: 06145
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: STEVE SANDIN
Licensee: HOTWELL US LTD
Region: 4
City: HOUSTON State: TX
County:
License #: 06145
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/15/2009
Notification Time: 15:55 [ET]
Event Date: 10/15/2009
Event Time: 14:15 [CDT]
Last Update Date: 10/15/2009
Notification Time: 15:55 [ET]
Event Date: 10/15/2009
Event Time: 14:15 [CDT]
Last Update Date: 10/15/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CHUCK CAIN (R4DO)
MARK DELLIGATTI (FSME)
CHUCK CAIN (R4DO)
MARK DELLIGATTI (FSME)
POTENTIAL LOST SEALED SOURCE CONTAINING 1.8 CURIES TRITIUM
The following information was received from the State of Texas via email:
"On June 29, 2009 Hotwell US LTD received a new shipment of two tritium well logging tools from their manufacturer in Austria. The tools each contain a 1.8 Curies (Ci) tritium sealed source inside a 15,000 psi pressure housing. These tools were slated for sale and delivery to Competition Wireline (NRC License No. 25-27802-1) out of Billings, Montana. After arriving at the facility in Houston, Texas, the tools were checked and shipped via [common carrier] to Competition Wireline. One tool (No. 33264) arrived at Competition Wireline on July 1, 2009. On July 6, 2009, Competition Wireline verified to Hotwell US LTD that the other tool (No. 33284) had been received. On October 13, 2009 Competition Wireline reported to Hotwell US LTD that after a general inventory of equipment, they could not locate one of the tools (No. 33284). The licensee has alleged that [the common carrier] never delivered the tool and found that it was last tracked to Memphis, Tennessee. [The common carrier] now shows the package as 'In Transit'. Competition Wireline has notified [the common carrier], and [the common carrier] is conducting an investigation into the location of the package.
The missing tool is described as follows:
" Tool No. 33284
Monoblock No.: 99448
Model No.: ING-10-50-120-TBT
Description: 84 x12 x8 Black Crate
"Texas Incident Number I-8677."
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
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 following information was received from the State of Texas via email:
"On June 29, 2009 Hotwell US LTD received a new shipment of two tritium well logging tools from their manufacturer in Austria. The tools each contain a 1.8 Curies (Ci) tritium sealed source inside a 15,000 psi pressure housing. These tools were slated for sale and delivery to Competition Wireline (NRC License No. 25-27802-1) out of Billings, Montana. After arriving at the facility in Houston, Texas, the tools were checked and shipped via [common carrier] to Competition Wireline. One tool (No. 33264) arrived at Competition Wireline on July 1, 2009. On July 6, 2009, Competition Wireline verified to Hotwell US LTD that the other tool (No. 33284) had been received. On October 13, 2009 Competition Wireline reported to Hotwell US LTD that after a general inventory of equipment, they could not locate one of the tools (No. 33284). The licensee has alleged that [the common carrier] never delivered the tool and found that it was last tracked to Memphis, Tennessee. [The common carrier] now shows the package as 'In Transit'. Competition Wireline has notified [the common carrier], and [the common carrier] is conducting an investigation into the location of the package.
The missing tool is described as follows:
" Tool No. 33284
Monoblock No.: 99448
Model No.: ING-10-50-120-TBT
Description: 84 x12 x8 Black Crate
"Texas Incident Number I-8677."
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
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: 45437
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRIAN JOHNSON
HQ OPS Officer: STEVE SANDIN
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRIAN JOHNSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/15/2009
Notification Time: 17:13 [ET]
Event Date: 10/15/2009
Event Time: 14:49 [CDT]
Last Update Date: 10/15/2009
Notification Time: 17:13 [ET]
Event Date: 10/15/2009
Event Time: 14:49 [CDT]
Last Update Date: 10/15/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ERIC DUNCAN (R3DO)
ERIC DUNCAN (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO MINOR OIL SPILL TO THE MISSISSIPPI RIVER
An oil spill of less than 1/2 of a cup to the Mississippi River occurred while preparing for Intake Structure dredging activities. Hydraulic oil leaked out of a fitting for the dredging pump and entered the Mississippi River side of the Intake Screenhouse. A small oil sheen was noticed and collected using the pre-deployed absorbents. The fitting was repaired and no more oil is currently leaking. The Minnesota Pollution Control Agency and the National Response Center were notified.
The licensee notified the NRC Resident Inspector.
An oil spill of less than 1/2 of a cup to the Mississippi River occurred while preparing for Intake Structure dredging activities. Hydraulic oil leaked out of a fitting for the dredging pump and entered the Mississippi River side of the Intake Screenhouse. A small oil sheen was noticed and collected using the pre-deployed absorbents. The fitting was repaired and no more oil is currently leaking. The Minnesota Pollution Control Agency and the National Response Center were notified.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 45438
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: DAVID KARST
HQ OPS Officer: STEVE SANDIN
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: DAVID KARST
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/15/2009
Notification Time: 18:11 [ET]
Event Date: 10/15/2009
Event Time: 12:04 [CDT]
Last Update Date: 10/15/2009
Notification Time: 18:11 [ET]
Event Date: 10/15/2009
Event Time: 12:04 [CDT]
Last Update Date: 10/15/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ERIC DUNCAN (R3DO)
ERIC DUNCAN (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
MOMENTARY LOSS OF SHUTDOWN COOLING WITH AUTOSTART OF EMERGENCY DIESEL GENERATOR
"At 1204 power was lost to Safeguards Bus '5' and Emergency Diesel Generator 'A' started and re-energized Bus '5.'
"Event was caused by starting SI Pump 'A' to fill SI Accumulator 'A' which resulted in a Tertiary Auxiliary Transformer trip and lockout. At the time RHR Pump 'A' was in operation and tripped, RHR Pump 'B' was started within 2 minutes using the Abnormal Operating Procedure and flow restored to the RCS. RCS temperature decreased initially due to an increase in service water cooling and actions were taken to stabilize RCS Temperature.
"All equipment operated as expected for the voltage restoration to Safeguards Bus '5.'
"Both trains of RHR were declared inoperable as of 1204 [CDT] due to the loss of normal power supplies per Technical Specification 3.7. Emergency Busses were energized and both trains of RHR remained available for decay heat removal during this event."
The licensee informed the NRC Resident Inspector.
"At 1204 power was lost to Safeguards Bus '5' and Emergency Diesel Generator 'A' started and re-energized Bus '5.'
"Event was caused by starting SI Pump 'A' to fill SI Accumulator 'A' which resulted in a Tertiary Auxiliary Transformer trip and lockout. At the time RHR Pump 'A' was in operation and tripped, RHR Pump 'B' was started within 2 minutes using the Abnormal Operating Procedure and flow restored to the RCS. RCS temperature decreased initially due to an increase in service water cooling and actions were taken to stabilize RCS Temperature.
"All equipment operated as expected for the voltage restoration to Safeguards Bus '5.'
"Both trains of RHR were declared inoperable as of 1204 [CDT] due to the loss of normal power supplies per Technical Specification 3.7. Emergency Busses were energized and both trains of RHR remained available for decay heat removal during this event."
The licensee informed the NRC Resident Inspector.