| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/06/2007 - 04/09/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43273 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: SUMMIT ECS, INC.
Region: 1
City: CHARLOTTE State: NC
County:
License #: SC 777
Agreement: Y
Docket:
NRC Notified By: LEE COX
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/03/2007
Notification Time: 18:49 [ET]
Event Date: 04/03/2007
Event Time: 16:00 [EDT]
Last Update Date: 04/03/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HAROLD GRAY (R1)
DENNIS RATHBUN (FSME)
| Event Text TROXLER GAUGE DAMAGED DURING FIRE
At approximately 1600 hours, a propane tank at a construction site located at 15136 Rutan Lane in Charlotte, NC exploded. The resulting fire fully engulfed a pickup truck containing a Troxler moisture density gauge. NC Radiation Protection was informed at 1703 hours by NC Emergency Management of the incident and has dispatched an Inspector to the scene to assist Hazmat. The initial radiation readings provided by Hazmat show preliminary readings of .3 mr/hr (not sure whether this is contact or near the gauge).
* * * UPDATE PROVIDED BY LEE COX TO JEFF ROTTON AT 2205 ON 04/03/07 * * *
The North Carolina Radiation Protection Inspector is onsite at the scene of the explosion. The truck was damaged beyond repair and the Inspector was able to locate both gauge sources with survey instruments. The Troxler gauge is a model 3440 with a 40 millicurie Am-241:Be source and a 8 millicurie Cs-137 source. Both sources were located in the bed of the truck. The Am-241 source was outside the gauge housing and the Cs-137 source was still attached to the source handle/rod. Neither source was breached. The Inspector was able to use various retrieval instruments to pickup both sources and place them into a temporary transportation package created on the scene and use available material for shielding and packaging to secure the sources. The temporary transportation package was secured in the bed of a truck with a cab over the truck bed. Radiation readings in the cab of the truck and on the sides of the truck bed were background. Radiation readings at a distance of 1 meter from the package was < 2 mR/hr. The radiation reading on contact was 15 mR/hr. The truck with the damaged Troxler gauge was escorted by the NC Radiation Protection Inspector to the South Carolina licensee's site located at 3575 Center Circle, Fort Mill, SC 29715, South Carolina License # -777. The gauge manufacturer, Troxler, was contacted and will be sending a DOT approved transportation container so that the licensee can return the damaged gauge to the manufacturer. NRC Region 1 (Kinneman) and the State of South Carolina were notified by the North Carolina Radiation Protection Office.
Notified R1DO (Gray) and FSME EO (Rathbun) |
| General Information or Other | Event Number: 43274 | Rep Org: NEW MEXICO RAD CONTROL PROGRAM
Licensee: NEW MEXICO RAD CONTROL PROGRAM
Region: 4
City: ALBUQUERQUE State: NM
County:
License #:
Agreement: Y
Docket:
NRC Notified By: WALTER MEDINA
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/03/2007
Notification Time: 18:05 [ET]
Event Date: 04/01/2007
Event Time: [MDT]
Last Update Date: 04/03/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
DENNIS RATHBUN (FSME)
ILTAB (via e-mail) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text SEVERAL CHECK SOURCES STOLEN FROM A UTILITY TRAILER
The following information was received via e-mail from the State of New Mexico:
"[NM Radiation Protection Control Bureau] received notification at approximately 2:30 p.m. that seven (7) sets of button check sources licensed to the NM Radiation Control Bureau were being stored in a NM Department of Health utility trailer that was stolen in Albuquerque, NM over the weekend. These sources are used as check sources for survey meters (also stolen) during training sessions for emergency response personnel at facilities along the WIPP routes in NM. This incident is being investigated by NM State Police and the Albuquerque Police Department. Personnel from the Department of Homeland Security, the NM Department of Health, and the WIPP Emergency Response Program of the NM Radiation Control Bureau are also involved in the investigation and will provide a press release. The following sources were reported missing:
7-10 nanoCurie Pu-239
7-10 nanoCurie Sr-90 (exempt)
7-1 microCurie Cs-137 (exempt)
"More details will be provided as they become available."
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. |
| General Information or Other | Event Number: 43275 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: LAFAYETTE GENERAL MEDICAL CENTER
Region: 4
City: LAFAYETTE State: LA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: PETE SNYDER | Notification Date: 04/04/2007
Notification Time: 12:02 [ET]
Event Date: 04/03/2007
Event Time: [CDT]
Last Update Date: 04/04/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
MICHELE BURGESS (FSME)
ILTAB (e-mail) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN PALLADIUM SEEDS
The State of Louisiana received a report from a licensee representative that 101 Palladium 103 seeds, with a total activity of 132 millicuries, were stolen. The seeds were stolen from a truck at 2235 Highway 178 in Sunset, LA. The seeds had been accepted by the licensee from the shipper and were going to transported to the hospital by the licensee representative.
The licensee notified the Louisiana State Police and local law enforcement and is following up on the incident.
* * * UPDATE ON 4/4/07 AT 1630 EDT FROM PATE TO SNYDER * * *
The following information was received via e-mail from the State of Louisiana:
At the time of the theft the truck was parked at the residence of the licensee's Radiation Safety Officer (RSO). The RSO contacted the St. Landry Parish Sheriff and the Louisiana State Police. The seeds were in the vehicle on the rear seat inside a red, padlocked, metal tool chest labeled as radioactive material. The approximate dimensions of the tool chest are 1.5 to 2 feet long and 8 to 10 inches wide. The seeds were contained in seven plastic sleeves that were attached to the inside of one stainless steel container that was inside another stainless steel container.
Louisiana Department of Environmental Quality has dispatched three inspectors out to search the area where the sources were stolen with instrumentation. "If the Palladium sources were piled together outside of their shielded containers, this would result in a radiation exposure roughly 16.6 [millirem/hour] at one foot.
"[The RSO] has stated that the facility will be notifying the public by television and newspapers."
Notified R4DO (C. Cain) and FSME EO (D. Rathbun).
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. |
| General Information or Other | Event Number: 43277 | Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: UTAH POWER AND LIGHT COMPANY
Region: 4
City: PRICE State: UT
County:
License #: UT 1800163
Agreement: Y
Docket:
NRC Notified By: GWEN GALLOWAY
HQ OPS Officer: PETE SNYDER | Notification Date: 04/04/2007
Notification Time: 19:43 [ET]
Event Date: 03/02/2007
Event Time: 13:30 [MST]
Last Update Date: 04/04/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
DENNIS RATHBUN (FSME)
| Event Text AGREEMENT STATE REPORT - FIXED LEVEL GAUGE SOURCE FAILURE TO RETRACT
The following information was reported to the NRC via facsimile:
The Utah Division of Radiation Control was initially notified by telephone on March 3, 2007 at about 10:20 am MST by the licensee's consultant that a source of a fixed level gauge at the Hunter Power Plant near Castle Dale, Utah failed to retract into the safe shielded position. The gauge is a Texas Nuclear Model 5197, Serial Number 1305 level gauge containing 100 millicuries of Cs-137. The licensee contacted their service consultant who discovered that the handle on the gauge was bent. The consultant indicated that it appeared that someone had attempted to turn the handle on the gauge without pulling the button. This act had apparently bent the handle. When the licensee had attempted to close the device properly, the bent handle did not allow the drive cable to align properly with the source to retract it.
This incident is being tracked by the State as Utah Report ID No. UT-07-0002. |
| Power Reactor | Event Number: 43282 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ALAN D. RABENOLD
HQ OPS Officer: PETE SNYDER | Notification Date: 04/05/2007
Notification Time: 21:22 [ET]
Event Date: 04/05/2007
Event Time: [EDT]
Last Update Date: 04/06/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
LAURA KOZAK (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text POTENTIALLY CONTAMINATED PERSON WITH A BACK INJURY TRANSPORTED TO LAKE EAST HOSPITAL
"At 2005, an injury occurred to a worker when the individual fell and injured his back. At 2122, the worker was attended by local Emergency Medical Personnel who transported the individual to our local Hospital. Due to his back injury his back will not be able to be completely monitored until arrival to the hospital. The individual is being classified as potentially contaminated. Radiation [Protection] personnel are accompanying the victim on the ambulance and to the local hospital emergency room to aid in radiological assessment.
"Due to our procedures we will be making notifications to the State Of Ohio and the local county Emergency Management Agencies of the incident. Due to the offsite notifications a 4 hour non-emergency call is required."
The individual was a contractor onsite for outage support.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 2249 ON 4/5/07 FROM A. RABENOLD TO SNYDER * * *
"The contractor individual was found in the Containment Drywell 630 foot elevation. He fell off of scaffolding approximately 4-5 feet to the grating. When the medical personnel arrived at the scene they found him unconscious. He regained [consciousness] when medical personnel arrived at the scene.
"At 2218 [the licensee received a] report from Radiation Protection personnel that the individual was not contaminated."
Notified R3DO (L. Kozak).
* * * Update on 04/06/07 at 1130 EDT from M. Nemcek to MacKinnon * * *
The injured person was found not to have contamination on him but it was reported to Perry Nuclear Power plant that fixed contamination was found on his Protective Clothing (PC), Safety Belt and Tool Belt. Fixed contamination on the PC direct contact reading was between 100 to 150 cpm. Fixed direct on contact contamination on the Safety Belt & the Toll Belt was between 100 to 500 cpm. No contamination found in the ambulance or in the Hospital. NRC Resident Inspector was left a message of this information by the licensee. NRC R3DO (L. Kozak) notified. |
| Power Reactor | Event Number: 43285 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TOM LOUGHRAN
HQ OPS Officer: JOHN MacKINNON | Notification Date: 04/06/2007
Notification Time: 11:59 [ET]
Event Date: 04/06/2007
Event Time: 11:11 [EDT]
Last Update Date: 04/06/2007 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
HAROLD GRAY (R1)
M.J. ROSS-LEE (NRR)
SAM COLLINS (R1)
JIM DYER (NRR)
HOLTZ (DHS)
PARIS (USDA)
TURNER (DOE)
DUNKER (FEMA)
TURNER (HHS)
WILSON (EPA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 93 | Power Operation | 0 | Hot Standby | Event Text MAIN GENERATOR TRANSFORMER EXPLOSION - NO IMPACT ON PLANT SAFETY RELATED SYSTEMS
At 1143 on 4/6/07 the licensee declared an Unusual Event due to a main transformer explosion in the protected area. The event was declared in accordance with EAL 8.2.2. Unit 3 automatically tripped due to a load reject at the main generator. The Unit is currently stable at normal operating temperature and pressure. Decay heat is being removed via the steam dumps to the main condenser. All emergency diesel generators are available if needed but safety buses are currently supplied with offsite power.
At the transformer site the deluge system actuated and the fire brigade responded. The fire was out at the time of the report
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1232 ON 4/6/07 FROM LAUGHLIN TO HUFFMAN * * *
The offsite local fire department was called by the licensee but their support was not needed and they were released.
* * * UPDATE AT 1259 ON 4/6/07 FROM LAUGHLIN TO HUFFMAN * * *
The licensee exited Unusual Event at 1247 based on the fact that the fire was confirmed to be extinguished, there was no damage to safety equipment and the plant was in a safe and stable condition.
* * * UPDATE AT 1440 ON 4/6/07 FROM PRUSSMAN TO KNOKE * * *
"On April 6 at 1143 hours, an unusual event was declared based on Emergency Action Level 8.2.2, an explosion in the 'B' phase of the 31 main transformer. This is a one hour reportable event to the NRC made at 1159 hours. This is an update of EN 43285. The NUE was terminated at 1247 hours.
"The State and County were also notified of the unusual event. A press release was made. Although no one was injured as a result of this event, a four hour report is being made since this is related to on-site personnel safety. The main generator tripped and this resulted in a consequential reactor trip. The Reactor Protection System shut down the reactor at 1109 hours, a four hour report. The plant operated as designed and the Auxiliary Feedwater System actuated, an eight hour report. The fire was reported to the Control Room at 1111 hours. The fire was put out in less than 15 minutes.
"The event is currently under investigation."
The header information in this event was revised as a result of this update to indicate 'Offsite Notification.' |
| Power Reactor | Event Number: 43286 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRIS SKINNER
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/06/2007
Notification Time: 14:50 [ET]
Event Date: 01/11/2007
Event Time: 12:11 [EDT]
Last Update Date: 04/06/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
HAROLD GRAY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INITIATION OF INVALID PRIMARY CONTAINMENT ISOLATION SIGNALS
"This is not an L.E.R. The report is being made to the NRC under 10 CFR 50.73(a)(2)(iv)(A), and the 60 day telephone notification option under 10 CFR 50.73(a)(1). The event included invalid 'general containment isolation signals affecting containment isolation valves in more than one system' as discussed in 10 CFR 50.73(a)(2)(iv)(B).
"(a) 'The specific train(s) and systems that were actuated.'
"On January 11, 2007 at 12:11 hours, Unit 2 received invalid Primary Containment Isolation signals to both Group 5 (RHR Shutdown Cooling System Isolation valves) and Group 10 (Reactor Core Isolation System Isolation valves) during instrumentation surveillance testing. While performing testing of the Division I Group 5 and Group 10 isolation functions of the RHR ambient temperature instrumentation, Technicians omitted a procedural step, resulting in the invalid signal actuations.
"(b) 'Whether each train actuation was complete or partial.'
"The event resulted in closure of the RCIC steam supply header outboard containment isolation valve. The Division 1 RHR Shutdown Cooling System isolation valves were already closed at the time of the isolation signal.
"(c) 'Whether or not the system started and functioned as designed,'
"The Primary Containment Isolation instrumentation logic and associated valve closure function (for RCIC) actuated as designed. The reporting of this event exceeds the 60 day notification requirement as a result of initially not fully understanding the impact of the invalid signal actuation. This condition has been entered into the Corrective Action Program."
The licensee notified the NRC Resident Inspector. |
| General Information or Other | Event Number: 43287 | Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR INSTRUMENTS INC.
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID T. ROBERTS
HQ OPS Officer: PETE SNYDER | Notification Date: 04/06/2007
Notification Time: 16:58 [ET]
Event Date: 04/06/2007
Event Time: [CDT]
Last Update Date: 04/06/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
LAURA KOZAK (R3)
HAROLD GRAY (R1)
CHARLES R. OGLE (R2)
CHUCK CAIN (R4)
OMID TABATABAI (NRR)
| Event Text CERTAIN MODEL 1152 PRESSURE TRANSMITTERS MAY LEAK ABOVE 2000 PSI PROCESS PRESSURE
Model 1152 pressure transmitters shipped to facilities between June 12, 2006 and December 20, 2006 may exhibit leakage from a threaded connection interface between the flange and the vent/drain valve seat if subjected to a process pressure greater than 2000 psi. Consequently, performance to published hydrostatic test specifications, or sealing at the maximum working pressures above 2000 psi cannot be assured.
The following potentially affected utilities were identified: Ameren UE, Alabama Power Co., Detroit Edison Co., Dominion, Entergy, Exelon Generation Co., First Energy Corp., FPL Duane Arnold LLC, Georgia Power Co., Nuclear Management Co., Omaha Public Power District, Pacific Gas and Electric, Pennsylvania Power and Light Co., Progress Energy Florida Inc., South Carolina Electric and Gas, and Tennessee Valley Authority. |
| Power Reactor | Event Number: 43289 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: EDWARD BERTRAM
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/06/2007
Notification Time: 19:01 [ET]
Event Date: 04/06/2007
Event Time: 16:00 [EDT]
Last Update Date: 04/06/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
CHARLES R. OGLE (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION - SPILL OF MOLYBDATES FROM CCW.
"This is a non-emergent event.
"At 1600 EDT, Unit 5 (conventional Co-Generation plant) reported to Florida state agencies a spill of their Closed Cooling Water due to a failure of a system valve. The magnitude of the spill was approximately 2500 gal of cooling water which contained Molybdates. The water was contained in the site's normal drain system.
"Agencies notified:
Florida State Warning Point
Florida Department of Environmental Protection - District
Florida Department oh Environmental Protection - District Citing Office
"The actual event occurred at 0822. Turkey Point Control Room was informed of the notification at 1610."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 43290 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JEFF GARDENER
HQ OPS Officer: PETE SNYDER | Notification Date: 04/07/2007
Notification Time: 17:26 [ET]
Event Date: 04/07/2007
Event Time: 13:44 [PDT]
Last Update Date: 04/07/2007 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
CHUCK CAIN (R4)
CATHERINE HANEY (NRR)
THOMAS BLOUNT (IRD)
JIM DYER (NRR)
BRUCE MALLET (R4)
FROST (DHS)
SWEETSER (FEMA)
JIMENEZ (USDA)
PAULEY (DOE)
WHITE (HHS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 95 | Power Operation | 95 | Power Operation | Event Text FIRE IN THE REACTOR PROTECTION SYSTEM DIVISION 2 EQUIPMENT ROOM
"On April 7, 2007 at 1330 Pacific Daylight Time (PDT) Columbia Generating Station (CGS) experienced an electrical fire in the Reactor Protection System (RPS) Division 2 equipment room. Currently, reactor level is stable and being controlled with the feedwater system. Reactor pressure is stable and being controlled with the turbine bypass valves in automatic. All safety systems are functional and there were no ECCS system actuations. At this time the plant is stable and the source of the fire was an electrical transformer which feeds the alternate electrical power supply to a Division 2 inverter isolation logic."
Plant operation was not impacted and the plant continues to operate at about 95% power. The first responder on-site extinguished the fire with a hand held fire extinguisher at about 1339 local time. The licensee has informed the NRC Resident Inspector.
* * * UPDATE AT 1758 EDT ON 4/7/07 FROM F. SCHILL TO P. SNYDER * * *
The Emergency Action Level (EAL) entry condition for the Alert was a 'report by plant personnel of visible damage to equipment contained in a safe shutdown building' EAL 9.2.A.1. The equipment damaged was the backup power supply to the inverter. CGS has a fire watch established in the area to watch for reflash.
* * * UPDATE AT 2024 EDT ON 4/7/07 FROM F. SCHILL TO P. SNYDER * * *
The Alert condition was terminated at 1721 PDT based on the fact that no reflash was seen by the fire watch, the extent of the equipment damage is understood and the area is now cool.
Notified: R4DO (Cain), NRR EO (Haney), IRD Mgr. (Blount), R4 (Gwynn), DHS (Akers), FEMA (Sweetser), USDA (Jimenez), HHS (Dalziel), EPA (Natl. Resp. Cntr. - Crews). |
| Power Reactor | Event Number: 43291 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: RYAN STOUT
HQ OPS Officer: JOHN MacKINNON | Notification Date: 04/09/2007
Notification Time: 04:26 [ET]
Event Date: 04/08/2007
Event Time: 22:32 [PDT]
Last Update Date: 04/09/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
CHUCK CAIN (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 95 | Power Operation | 85 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
"Energy Northwest is reporting initiation of a planned shutdown of Columbia Generating Station Pursuant to 10 CFR 50.72(b)(i), 'The initiation of any nuclear plant shutdown required by the plant's technical specifications.' This plant shutdown is undertaken prior to 1032 PDT on 4/9/07 which is the expiration of the completion time of Technical Specification Limiting Condition for Operation 3.8.7 Required Action C. This plant shutdown is undertaken due to complications from recovery of the failure of a backup power supply to power converter E-IN-2A/2B reported in event notification # 43290."
The NRC Resident Inspector was notified of this event by the licensee. | |