NRC Current Event Notification Report for August 29, 2011

Search NRC

Report a Safety Concern

Current Event Notification Report for August 29, 2011 U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/26/2011 - 08/29/2011 ** EVENT NUMBERS ** 47091 47181 47196 47199 47200 47201 47202 47203 47205 47207 47208 47209 47210 47211 47212 47213 47214 Power Reactor Event Number: 47091 Facility: PRAIRIE ISLAND Region: 3 State: MN Unit: [1] [2] [ ] RX Type: [1] W-2-LP,[2] W-2-LP NRC Notified By: GENE DAMMANN HQ OPS Officer: STEVE SANDIN Notification Date: 07/23/2011 Notification Time: 23:20 [ET] Event Date: 07/23/2011 Event Time: 19:00 [CDT] Last Update Date: 08/26/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION Person (Organization): ERIC DUNCAN (R3DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N Y 100 Power Operation 100 Power Operation 2 N Y 100 Power Operation 100 Power Operation Event Text OFFSITE NOTIFICATION DUE TO UNMONITORED RELEASE OF TRITIUM TO SEPTIC SYSTEM "It was discovered that water containing tritium from a secondary system steam leak has been periodically disposed of via the septic system versus the normally monitored turbine building sump effluent path. The tritium amount was 8.00 E-5 microcuries per milliliter. The tritium sample is consistent with normal secondary plant samples. Since November, 2010, there have been no abnormal tritium results from the septic system. There was also MPA (29.7 parts per million) which is a pH additive. "The septic system is monitored on a monthly basis but is not a normal path for discharge of equipment related fluid leakage. The steam has been condensed and collected in a 5 gallon pail that is periodically emptied by crew personnel. Management just became aware that there were instances where disposal of the water was to the septic system. This practice has been halted. The steam leak has been active since November of 2010. "This is being reported due to the potential for being an unusual or abnormal release of radioactive effluent. "The NRC resident has been informed." The licensee will also inform state and local agencies of this event. * * * UPDATE FROM BILL SCHALLER TO DONALD NORWOOD AT 1505 EDT ON 8/26/11 * * * "This is an update to EN 47091 (Water containing tritium from secondary system leak disposed of via septic system) submitted at 2320 EDT on 7/23/2011. "The fluid in the septic system at Prairie Island Nuclear Generating Plant is removed from site by a vendor, who transports the fluid to the Red Wing, MN Wastewater Treatment Plant where it is processed prior to being discharged. "The NRC Resident Inspector has been informed. Notified R3DO (Passehl). Power Reactor Event Number: 47181 Facility: NORTH ANNA Region: 2 State: VA Unit: [1] [2] [ ] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: LEE BARON HQ OPS Officer: ERIC SIMPSON Notification Date: 08/23/2011 Notification Time: 14:24 [ET] Event Date: 08/23/2011 Event Time: 14:03 [EDT] Last Update Date: 08/26/2011 Emergency Class: ALERT 10 CFR Section: 50.72(a) (1) (i) - EMERGENCY DECLARED Person (Organization): MALCOLM WIDMANN (R2DO) JOHN THORP (NRR) SCOTT MORRIS (IRD) JACK GROBE (NRR) VICTOR MCCREE (R2RA) JAMES (DHS) ERWIN (FEMA) REDINGTON (USDA) FOOTE (DOE) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 A/R Y 100 Power Operation 0 Hot Standby 2 A/R Y 100 Power Operation 0 Hot Standby Event Text ALERT DECLARED DUE TO AN EARTHQUAKE IN THE AREA AND A LOSS OF OFFSITE POWER At 1403 hrs. EDT, North Anna Power Station declared an Alert due to significant seismic activity onsite. The Alert was declared under EAL HA6.1. Both units experienced automatic reactor trips from 100% power and are currently stable in Mode 3. All offsite electrical power to the site was lost. All four emergency diesel generators (EDG) automatically started and loaded and provided power to the emergency buses. While operating, the 2H EDG developed a coolant leak and was shutdown. As a result, the licensee added EAL SA1.1 to their declaration. All control rods inserted into the core. Decay heat is being removed via the steam dumps to atmosphere. No personnel injuries were reported. * * * UPDATE FROM ROBERT RINK TO HOWIE CROUCH AT 1116 EDT ON 8/24/11 * * * The licensee has downgraded the Alert to a Notification of Unusual Event based on equipment alignments and inspection results. The licensee notified R2 IRC. Notified IRD (Marshall), NRR (Thorp), FEMA (Hollis), DHS (Inzer), USDA (Ferezan), HHS (Willis) and DOE (Parsons). * * * UPDATE FROM ROBERT RINK TO HOWIE CROUCH AT 1317 EDT ON 8/24/11 * * * The licensee has exited the Notification of Unusual Event at 1315 EDT. The exit criteria was that all inspections and walkdowns were completed and plant conditions no longer meet the criteria for a NOUE. Notified R2DO (Widmann), IRD (Marshall), NRR (Thorp), FEMA (Hollis), DHS (Inzer), USDA (Ferezan), HHS (Willis) and DOE (Jackson). * * * UPDATE FROM DON TAYLOR TO DONALD NORWOOD AT 1405 EDT ON 8/26/11 * * * "This notification is to report new information identified post event that a condition existed which met the emergency plan criteria but was not declared. On August 23 at 1403 EDT, North Anna Power Station declared an Alert due to seismic activity onsite. The Alert was declared under Emergency Action Level (EAL) HA6.1 "Other conditions existing which in the judgment of the SM warrant declaration of an alert. Initial review of seismic response data from the earthquake on 8/23/11 (1348 hours) indicates that design spectrum input assumptions (i.e. Design Basis Earthquake [DBE] limits) may have been exceeded above 5 HZ. This would have resulted in classification of an Alert under EAL HA1.1. "No significant equipment damage to safety related systems (including class I structures) has been identified through site walk-downs nor has equipment degradation been detected through plant performance and surveillance testing following the earthquake." The licensee notified the NRC Resident Inspector. The licensee also plans on notifying the State Emergency Operations Center and the Louisa County County Administrator. Notified R2DO (Widmann) and NRR EO (Bahadur). Power Reactor Event Number: 47196 Facility: NORTH ANNA Region: 2 State: VA Unit: [1] [2] [ ] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: BEN SCHRUM HQ OPS Officer: CHARLES TEAL Notification Date: 08/25/2011 Notification Time: 01:48 [ET] Event Date: 08/25/2011 Event Time: 01:18 [EDT] Last Update Date: 08/28/2011 Emergency Class: UNUSUAL EVENT 10 CFR Section: 50.72(a) (1) (i) - EMERGENCY DECLARED Person (Organization): MALCOLM WIDMANN (R2DO) VICTOR MCCREE (R2RA) JACK GROBE (NRR) JANE MARSHALL (IRD) JOHN KNOX (DHS) MIKE BLANKENSHIP (FEMA) 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 N 0 Hot Standby 0 Hot Standby Event Text UNUSUAL EVENT DECLARED DUE TO AN AFTERSHOCK EARTHQUAKE On August 25th at 0118 EDT, North Anna Power Station declared an Unusual Event due to seismic activity onsite (EAL HU 1.1). Both units are currently shutdown and electrical power is being supplied from offsite. There were no personnel injuries. There was no radiological release. Site structure and system inspections are in progress. No damage has been identified. The NRC Resident Inspector and state and local authorities have been notified. * * * UPDATE FROM JOHN BALTOR TO ERIC SIMPSON AT 1215 EDT ON 8/25/11 * * * At 1149 EDT another minor tremor was felt at the station. No geological information is available at this time. There is no immediate indication of any equipment damage. Walkdowns are being performed at this time. North Anna Emergency Management indicated that there was currently no plan to secure from the Notification of Unusual Event until there is sufficient indication that the station will not experience any additional aftershocks to prevent having to re-enter an emergency status once exited. The current status of North Anna, Unit 1 is Mode 5. Unit 2 is in Mode 3 in preparation for cool down. The licensee will verify that the NRC Resident Inspector is notified. Notified IRD (Marshall), NRR (Thorp), and R2DO (Widmann). * * * UPDATE AT 1546 EDT ON 8/28/11 FROM LINDNER TO HUFFMAN * * * The licensee has exited from its unusual event at 1536 EDT on 8/28/11 based on the cessation of any further seismic activity. The licensee has notified appropriate state and local authorities and will notify the NRC Resident Inspector. Notified R2DO (Widmann), NRR (Bahadur), IRD (Marshall), FEMA (Vitale) and DHS (Hill). Power Reactor Event Number: 47199 Facility: PILGRIM Region: 1 State: MA Unit: [1] [ ] [ ] RX Type: [1] GE-3 NRC Notified By: ROBERT O'NEILL HQ OPS Officer: BILL HUFFMAN Notification Date: 08/26/2011 Notification Time: 15:02 [ET] Event Date: 08/26/2011 Event Time: 13:45 [EDT] Last Update Date: 08/26/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION Person (Organization): PAUL KROHN (R1DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N Y 100 Power Operation 100 Power Operation Event Text PRESS RELEASE RELATED TO HURRICANE PREPARATIONS AT THE PILGRIM SITE "At approximately 1345 EDT, on August 26, 2011, Entergy Corporation issued a press release regarding ongoing preparations at Pilgrim Station for hurricane Irene currently located 300 miles SSW of Cape Hatteras, North Carolina traveling in a northerly direction at approximately 14 miles per hour. The purpose of the press release is to re-assure the public regarding the safety and security of the facility and the extent of preparations that are in progress. Current plant operation is not impacted and the release of this information does not indicate a current threat to the facility or the health and safety of the public. "The licensee has notified the NRC Resident Inspector. "This four (4) hour report is being made in accordance with 10 CFR 50.72(b)(2)(xi). "State and local notifications will be made coincident with the Issuance of this Event Report." Power Reactor Event Number: 47200 Facility: VERMONT YANKEE Region: 1 State: VT Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: JIM KRITZER HQ OPS Officer: DONG HWA PARK Notification Date: 08/26/2011 Notification Time: 16:22 [ET] Event Date: 08/26/2011 Event Time: 13:45 [EDT] Last Update Date: 08/26/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION Person (Organization): PAMELA HENDERSON (R1DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N Y 100 Power Operation 100 Power Operation Event Text PRESS RELEASE REGARDING LICENSEE HURRICANE PREPARATION ACTIVITIES "At approximately 1345 EDT, on 8/26/2011, Entergy Corporation issued a press release regarding ongoing preparations at Vermont Yankee Nuclear Power Station for hurricane Irene currently located approximately 300 miles SSW of Cape Hatteras, NC. "The purpose of the press release is to reassure the public regarding the safety and security of the facility and the extent of preparations that are in progress. Plant operation is not currently impacted, and the release of this information does not indicate a current threat to the facility or the health and safety of the public." The licensee has notified the NRC Resident Inspector. Power Reactor Event Number: 47201 Facility: NORTH ANNA Region: 2 State: VA Unit: [1] [2] [ ] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: PAGE KEMP HQ OPS Officer: BILL HUFFMAN Notification Date: 08/26/2011 Notification Time: 16:23 [ET] Event Date: 08/26/2011 Event Time: 13:00 [EDT] Last Update Date: 08/26/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION Person (Organization): MALCOLM WIDMANN (R2DO) 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 N 0 Hot Shutdown 0 Hot Shutdown Event Text UNANALYZED CONDITION BASED ON SEISMIC ACTIVITY THAT POTENTIALLY EXCEEDED DESIGN BASIS EARTHQUAKE MAGNITUDE On August 23, 2011 at 1351 hours, North Anna Power Station experienced a seismic activity event which resulted in a loss of offsite power and automatic reactor trip of both units. At 1403 hours, an Alert was declared. based on Shift Manager judgment, due to significant seismic activity on the site. Subsequent to the earthquake, both units were stabilized and offsite power was restored. Following the event, seismic data was retrieved from the installed monitoring system and shipped to the vendor to determine the response spectrum for the event. On August 26, 2011 at 1340 hours, initial reviews of the data determined that the seismic activity potentially exceeded the Design Basis Earthquake magnitude value above 5 Hz. Therefore, this is reportable per 10CFR50.72(b)(3)(ii) (B) for the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. North Anna Unit 1 is currently in Cold Shutdown with the Residual Heat Removal System providing core cooling. North Anna Unit 2 is currently in Hot Shutdown and will be taken to Cold Shutdown with the Residual Heat Removal System providing core cooling. No significant equipment damage to Safety Related system (including Class 1 Structures) has been identified through site walk-downs nor has equipment degradation been detected through plant performance and surveillance testing following the earthquake. Therefore, there is reasonable assurance that the Safety Related systems are fully functional. The Spent Fuel Pit cooling system also remains fully functional and the temperature of the Spent Fuel Pit remained unchanged during the event. The vendor will complete the analysis of the seismic data and this information will be utilized to address the long term actions following the earthquake. Power Reactor Event Number: 47202 Facility: FORT CALHOUN Region: 4 State: NE Unit: [1] [ ] [ ] RX Type: (1) CE NRC Notified By: NATHAN SEID HQ OPS Officer: BILL HUFFMAN Notification Date: 08/26/2011 Notification Time: 16:45 [ET] Event Date: 08/26/2011 Event Time: 12:36 [CDT] Last Update Date: 08/26/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE Person (Organization): MARK HAIRE (R4DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N N 0 Cold Shutdown 0 Cold Shutdown Event Text TECHNICAL SUPPORT CENTER UNAVAILABLE FOR EMERGENCY RESPONSE "During performance of IC-PM-VA-0200, Preventive Maintenance Air Flow Measurement of TSC Air Filter Unit VA-119, it was discovered that the required flow-rate of 2700 cfm and minimum overpressure of 0.1 inches of water in the TSC could not be achieved. Troubleshooting on VA-107, TSC Air Handling Unit, is in progress. "This condition renders the Technical Support Center unavailable for Emergency Planning Responses. Approved compensatory actions are to relocate personnel to alternate facilities if required. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(xiii) for Loss of Emergency Preparedness Capabilities." The licensee has notified the NRC Resident Inspector. Power Reactor Event Number: 47203 Facility: INDIAN POINT Region: 1 State: NY Unit: [2] [3] [ ] RX Type: [2] W-4-LP,[3] W-4-LP NRC Notified By: CHRIS BOHREN HQ OPS Officer: BILL HUFFMAN Notification Date: 08/26/2011 Notification Time: 16:56 [ET] Event Date: 08/26/2011 Event Time: 16:30 [EDT] Last Update Date: 08/26/2011 Emergency Class: NON EMERGENCY 10 CFR Section: OTHER UNSPEC REQMNT Person (Organization): PAMELA HENDERSON (R1DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 2 N Y 100 Power Operation 100 Power Operation 3 N Y 100 Power Operation 100 Power Operation Event Text HURRICANE NOTIFICATION PER TECHNICAL REQUIREMENTS MANUAL "A hurricane is within 500 nautical miles from Indian Point Energy Center with wind speed in excess of 87 knots. The National Weather Service has issued a hurricane warning for a hurricane with wind in excess of 87 knots (approximately 100 mph) within 500 nautical miles of the facility. Per the Technical Requirements Manual a prompt report shall be made to the NRC Incident Response Center within 1 hour of receipt of that hurricane warning." The licensee has notified the NRC Resident Inspector. Power Reactor Event Number: 47205 Facility: COMANCHE PEAK Region: 4 State: TX Unit: [1] [2] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: MIKE NIEMEYER HQ OPS Officer: PETE SNYDER Notification Date: 08/27/2011 Notification Time: 03:25 [ET] Event Date: 08/27/2011 Event Time: 01:56 [CDT] Last Update Date: 08/27/2011 Emergency Class: UNUSUAL EVENT 10 CFR Section: 50.72(a) (1) (i) - EMERGENCY DECLARED Person (Organization): MARK HAIRE (R4DO) ART HOWELL (R4) BRUCE BOGER (NRR) JANE MARSHALL (IRD) BRIAN MCDERMOTT (NSIR) SHER BAHADUR (NRR) MATTHEW HAHN (ILTA) JOHN KNOX (DHS) MICHAEL BLANKENSHIP (FEMA) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N Y 61 Power Operation 61 Power Operation 2 N Y 100 Power Operation 100 Power Operation Event Text UNUSUAL EVENT DECLARED DUE TO ENTRY INTO EAL HU 4-1 The licensee declared a Notice of Unusual Event per emergency plan condition HU 4-1 due to a security event. Contact the Headquarters Operations Officer for details. The licensee notified the NRC Resident Inspector. * * * UPDATE FROM DANNY BRADFORD TO PETE SNYDER AT 0410 EDT ON 8/27/11 * * * The Notice of Unusual Event has been terminated. Contact the Headquarters Operations Officer for details. Notified: R4DO (Haire), NRR (Bahadur), DHS (Knox), FEMA (Blankenship). Power Reactor Event Number: 47207 Facility: CALVERT CLIFFS Region: 1 State: MD Unit: [1] [2] [ ] RX Type: [1] CE,[2] CE NRC Notified By: BRIAN HAYDEN HQ OPS Officer: DONALD NORWOOD Notification Date: 08/27/2011 Notification Time: 21:06 [ET] Event Date: 08/27/2011 Event Time: 19:15 [EDT] Last Update Date: 08/27/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE Person (Organization): PAMELA HENDERSON (R1DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N Y 100 Power Operation 100 Power Operation 2 N Y 100 Power Operation 100 Power Operation Event Text EMERGENCY SIRENS OUT-OF-SERVICE "Sirens in St. Mary's and Calvert counties are out of service exceeding the minimum required of 19. Currently 44 sirens are out of service due to local power outages caused by the storm. Compensatory measures are in place for the affected counties. Route alerting will be used if necessary." The licensee notified the NRC Resident Inspector. Power Reactor Event Number: 47208 Facility: CALVERT CLIFFS Region: 1 State: MD Unit: [1] [ ] [ ] RX Type: [1] CE,[2] CE NRC Notified By: GREGG BUCKMASTER HQ OPS Officer: DONALD NORWOOD Notification Date: 08/27/2011 Notification Time: 23:27 [ET] Event Date: 08/27/2011 Event Time: 23:02 [EDT] Last Update Date: 08/28/2011 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)(3)(iv)(A) - VALID SPECIF SYS ACTUATION Person (Organization): PAMELA HENDERSON (R1DO) BRUCE BOGER (NRR) DAVE LEW (R1) SHER BAHADUR (NRR) JANE MARSHALL (IRD) JOHN KNOX (DHS) DAVID BARDEN (FEMA) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 A/R Y 100 Power Operation 0 Hot Standby Event Text UNUSUAL EVENT - TRANSFORMER EXPLOSION NEAR TURBINE BUILDING "At 2248 on 8/27/2011, the Unit 1 Reactor experienced an automatic trip due to loss of load. This trip occurred due to a phase to phase short on the main generator output step-up transformer that resulted from a large section of turbine building siding breaking loose in high winds from Hurricane Irene and impacting the transformer. This impact resulted in an explosion (briefly until the trip removed power from the impact area) which met emergency action level declaration criteria A.U.6.2.2, 'Unanticipated explosion within Protected Area resulting in visible damage to permanent structures or equipment.' The Unusual Event was declared at 2302, 8/27/2011. Follow-up investigation determined no fire resulted from the explosion. "Following the trip, Emergency Procedure, EOP-0, 'Post Trip Immediate Actions' was implemented. All safety functions were met during EOP-0 indicating an uncomplicated reactor trip response, allowing transition to EOP-1, 'Reactor Trip,' at 2300, 8/27/2011. During implementation of EOP-1, it was noted that #14 Containment Air Cooler had stopped running, as had #21 and #24 Containment Air Coolers on Unit 2. This was investigated and it was determined they had stopped running due to an instantaneous voltage drop that had occurred on the site distribution system during the phase to phase short event. This short duration voltage drop caused the Containment Air Coolers' controller to drop out and secure them. They were restarted without issue. "At 2400, 8/27/2011, numerous alarms on the 1A DG started to be received. These were investigated and it was found that water was intruding down the DG exhaust piping resulting in a DC ground. Based on these indications the 1A DG was declared inoperable and appropriate technical specifications implemented. "Besides the above issues plant response was as expected and EOP-1 was exited at 0130, 8/28/2011. [Procedure] OP-4, 'Shutdown from Power Operation to Hot Standby,' was implemented at that time. All control rods fully inserted on the reactor trip. The plant is in a normal post-trip electrical lineup. The licensee notified the NRC Resident Inspector. * * * UPDATE FROM GREGG BUCKMASTER TO PETE SNYDER AT 0811 EDT ON 8/28/11 * * * At 0755 EDT the licensee exited the Unusual Event condition based on the fact that they were able to inspect the area in the daylight and were satisfied that they knew the extent and nature of the damage. The licensee will notify the NRC Resident Inspector. Notified R1 IRC (Dentel), DHS (Hill), FEMA (Via). Power Reactor Event Number: 47209 Facility: COLUMBIA GENERATING STATION Region: 4 State: WA Unit: [2] [ ] [ ] RX Type: [2] GE-5 NRC Notified By: MICHAEL STODICK HQ OPS Officer: PETE SNYDER Notification Date: 08/28/2011 Notification Time: 02:41 [ET] Event Date: 08/27/2011 Event Time: 20:21 [PDT] Last Update Date: 08/28/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(B) - POT RHR INOP Person (Organization): MARK HAIRE (R4DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 2 N N 0 Cold Shutdown 0 Cold Shutdown Event Text SHUTDOWN COOLING TEMPORARILY ISOLATED "In accordance with 10 CFR 50.72 (b)(3)(v)(B) this event notification is being made to report an event that could have prevented the fulfillment of the safety function to remove residual heat. On August 27, 2011, following refueling, the plant was shutdown in Mode 4 with reactor coolant temperature being maintained 100-120 degrees F. Reactor coolant temperature was being controlled with RHR B operating in the Shutdown Cooling mode. At 2021 [EDT], an equipment failure caused a loss of Reactor Protection System (RPS) B resulting in a closure of RHR-V-9 (RHR Shutdown Cooling Inboard Isolation Valve), interrupting shutdown cooling flow. Operators transferred RPS B to the alternate power supply and restored RHR B to shutdown cooling. Shutdown cooling was out of service for 34 minutes. "During the 34 minute interruption of shutdown cooling, reactor coolant temperature rose from 107 degrees F to 111 degrees F. Following restoration of shutdown cooling, reactor coolant temperature was restored. All containment isolations resulting from the loss of RPS B occurred as expected. Further investigation is ongoing to determine the cause of the equipment failure that caused the loss of RPS B." The licensee notified the NRC Resident Inspector. Power Reactor Event Number: 47210 Facility: SOUTH TEXAS Region: 4 State: TX Unit: [1] [ ] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: ROBERT LANE HQ OPS Officer: VINCE KLCO Notification Date: 08/28/2011 Notification Time: 03:38 [ET] Event Date: 08/28/2011 Event Time: [CDT] Last Update Date: 08/28/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION Person (Organization): MARK HAIRE (R4DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N Y 100 Power Operation 100 Power Operation Event Text AUTOMATIC ACTUATION OF AN EMERGENCY DIESEL GENERATOR "At 2130 [EDT] on August 27, 2011, an automatic actuation of the Unit 1 Train A emergency diesel generator occurred due to an actuation signal from the load sequencer. The Train A 4160 kV emergency bus transferred to the emergency diesel generator and all Train A emergency loads required for Mode 2 started and sequenced onto the Train A 4160 KV emergency bus except the 480 volt center breaker to the bus E1A2 that did not close. The load sequencer is designed upon the receipt of a safety injection actuation and/or loss of offsite power to provide a signal to strip loads from the 4160 kV emergency bus and then, in sequence, to re-energize the associated 480 volt buses and to load engineering safety feature components onto the 4160 kV and associated 480 volt emergency buses in a predetermined sequence. Per 10 CFR 50.72(b)(3)(iv)(B), additional emergency safety features loads that actuated were the Train A reactor containment fan coolers and auxiliary feedwater system. "Unit 1 remains critical at 100 percent power. No emergency core cooling system injection occurred into the reactor coolant system. "The event occurred during surveillance testing when the Train A sequencer was taken from the AUTO Test position to the local position. It is not understood why the actuation occurred. In addition, it is not understood why the 480 volt load center breaker to the bus E1A2 did not close. "The 480 volt bus E1A2 was re-energized at 2308 [EDT] on August 27, 2011. The Train A 4160 kV bus was restored to the offsite power source at 0150 [EDT] on August 28, 2011 and the Train A emergency diesel generator and engineering safety features loads were restored to their normal condition at 0201 [EDT] on August 28, 2011. "With the Train A sequencer non-functional, the following Train A components are inoperable: 1) High Head Safety Injection Pump 1A; 2) Low Head Safety Injection Pump 1A; 3) Containment Spray Pump 1A; 4) RCFC [Reactor Containment Fan Cooler] Fan 11A; 5) RCFC Fan 12A; 6) Component Cooling Water Pump 1A; 7) Essential Cooling Water Pump 1A; 8) Aux Feedwater Pump 11; 9) Control Room/Elect. Aux Bldg HVAC; 10) Ess [Essential] Chiller 12A; and 11) ESF Diesel Generator 11. "Although these components will not automatically start on a safety injection signal or loss of offsite power, these loads can be manually actuated. Engineered Safety Features Trains B and C remain operable." The licensee notified the NRC Resident Inspector. Power Reactor Event Number: 47211 Facility: PEACH BOTTOM Region: 1 State: PA Unit: [2] [3] [ ] RX Type: [2] GE-4,[3] GE-4 NRC Notified By: BRAD POWELL HQ OPS Officer: VINCE KLCO Notification Date: 08/28/2011 Notification Time: 06:35 [ET] Event Date: 08/28/2011 Event Time: 05:15 [EDT] Last Update Date: 08/28/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION Person (Organization): PAMELA HENDERSON (R1DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 2 N Y 100 Power Operation 100 Power Operation 3 N Y 91 Power Operation 91 Power Operation Event Text EMERGENCY SIRENS OUT OF SERVICE "PBAPS [Peach Bottom Atomic Power Station] Control Room was notified of a loss of greater than 25% of sirens after severe storms in the area associated with Hurricane Irene. 51 of 97 Emergency Plan Zone (EPZ) sirens are unavailable in York County and Hartford County. Actions are currently being taken to restore unavailable sirens." The licensee notified Pennsylvania and Maryland Emergency Management and York and Harford Counties. The licensee notified the NRC Resident Inspector. Power Reactor Event Number: 47212 Facility: MONTICELLO Region: 3 State: MN Unit: [1] [ ] [ ] RX Type: [1] GE-3 NRC Notified By: MICHAEL STIDMON HQ OPS Officer: PETE SNYDER Notification Date: 08/28/2011 Notification Time: 10:05 [ET] Event Date: 08/29/2011 Event Time: 06:00 [CDT] Last Update Date: 08/28/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE Person (Organization): DAVE PASSEHL (R3DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N Y 50 Power Operation 50 Power Operation Event Text TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE ACTIVITY "On 8/29/11, Monticello Nuclear Generating Plant's Technical Support Center (TSC) power supply will be isolated to perform a planned maintenance activity. The maintenance activity requires implementation of compensatory measures to maintain TSC functions during the activity. The compensatory measures include having the Emergency Director report to the Control Room and co-locating the remaining TSC staff at the EOF should an event be declared requiring ERO activation. The ERO has successfully previously demonstrated the ability to implement these compensatory measures. The maintenance activity is scheduled to be completed with the TSC returned to full functionality by the end of the dayshift on 8/29/11. The site Emergency Response Organization has been notified of the maintenance activity and instructed on the planned compensatory measures to be implemented during the activity. The licensee has notified the NRC Resident Inspector." Power Reactor Event Number: 47213 Facility: OYSTER CREEK Region: 1 State: NJ Unit: [1] [ ] [ ] RX Type: [1] GE-2 NRC Notified By: STEVE JOHNSTON HQ OPS Officer: VINCE KLCO Notification Date: 08/28/2011 Notification Time: 11:13 [ET] Event Date: 08/28/2011 Event Time: 08:58 [EDT] Last Update Date: 08/28/2011 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION Person (Organization): PAMELA HENDERSON (R1DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N N 0 Cold Shutdown 0 Cold Shutdown Event Text EMERGENCY SIRENS OUT OF SERVICE "Oyster Creek has lost 10 sirens in the Emergency Plan Zone. Communications with the Ocean County Office of Emergency Management has been conducted to inform them of the outage." The licensee has notified the NRC Resident Inspector. Power Reactor Event Number: 47214 Facility: INDIAN POINT Region: 1 State: NY Unit: [2] [3] [ ] RX Type: [2] W-4-LP,[3] W-4-LP NRC Notified By: JOHN DIGNAM HQ OPS Officer: BILL HUFFMAN Notification Date: 08/28/2011 Notification Time: 16:55 [ET] Event Date: 08/28/2011 Event Time: 10:00 [EDT] Last Update Date: 08/28/2011 Emergency Class: NON EMERGENCY 10 CFR Section: OTHER UNSPEC REQMNT Person (Organization): PAMELA HENDERSON (R1DO) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 2 N Y 100 Power Operation 100 Power Operation 3 N Y 100 Power Operation 100 Power Operation Event Text 24 HOUR NOTIFICATION OF POLLUTION DISCHARGE PERMIT NOTIFICATION "On August 28, 2011 at approximately 1000 EDT the Indian Point common discharge canal was reported to be overflowing. The overflow condition was caused by the elevated river water levels experienced during Hurricane Irene. The site SPDES (State Pollution Discharge Elimination System) permit requires the canal discharge to be subsurface. Since the overflow was not a subsurface discharge it constituted a SPDES permit violation. There was no failure or malfunction of the outfall structure, and by 1430 EDT river level had lowered enough that the discharge canal was again operating within normal limits. "The resident inspector has been notified. New York State Department of Environment Control has been notified."

Page Last Reviewed/Updated Monday, August 29, 2011

©2000-2011 NRC

Monday, August 29, 2011