Event Notification Report for March 28, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/27/2003 - 03/28/2003 ** EVENT NUMBERS ** 39558 39699 39705 39709 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39558 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/03/2003| | UNIT: [1] [] [] STATE: FL |NOTIFICATION TIME: 19:51[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 02/03/2003| +------------------------------------------------+EVENT TIME: 17:45[EST]| | NRC NOTIFIED BY: DAVE FIELDS |LAST UPDATE DATE: 03/27/2003| | HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |KERRY LANDIS R2 | |10 CFR SECTION: | | |AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION FILTER TRAIN INOPERABLE | | | | "Plant identified a condition which could render the Unit 1 Control Room | | Ventilation Filter Train inoperable. This filter train is designed to | | mitigate radiological conditions within the occupied Control Room during an | | accident. A distorted cover was identified on ventilation ductwork which | | failed to provide an adequate seal. The ductwork is under repair and | | investigation is in progress." | | | | The licensee notified the NRC resident inspector. | | | | *** RETRACTION ON 3/27/03 AT 0940 EST RECEIVED FROM DAVID FIELDS TO ARLON | | COSTA *** | | | | "FPL is retracting this notification based on a subsequent Generic Letter | | 91-18 operability analysis of the observed condition. The operability | | assessment determined that the postulated in-leakage from the distorted | | ductwork cover plate was bounded by the maximum allowable alternate source | | term methodology unfiltered in-leakage. The analysis concluded that the | | control room envelope continued to meet its required safety function with | | respect to dose. Therefore the condition does not meet 10 CFR 50.72 or | | 50.73 reporting requirements." | | | | The licensee notified the NRC resident inspector. | | | | Notified R2DO (Bernhard). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39699 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 03/25/2003| | UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 11:42[EST]| | RXTYPE: [1] CE |EVENT DATE: 03/25/2003| +------------------------------------------------+EVENT TIME: 11:21[EST]| | NRC NOTIFIED BY: KEN JOHNSON |LAST UPDATE DATE: 03/27/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: ALERT |MICHAEL PARKER R3 | |10 CFR SECTION: |BILL BATEMAN NRR | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOHN JOLICOEUR IRO | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT|DAVE BARDEN FEMA | |AINB 50.72(b)(3)(v)(B) POT RHR INOP |BLAIR SPITZBERG R4 | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |JAMES DYER RA | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALERT DECLARED DUE TO LOSS OF SHUTDOWN COOLING | | | | The reactor is shutdown for a refueling outage since 3/17/03. An alert | | declaration was made on 3/25/03 at 1121 EST due to loss of shutdown cooling. | | Time to boil is estimated to be less than fifty five (55) minutes. Plant | | status is degrading. There are no radioactivity releases in progress. The | | current wind direction is from 270 to 90 degrees. The wind speed is eight | | (8) miles per hour, class B stability with no precipitation. Mitigating | | responses by the Licensee are in progress. | | | | The U.S. NRC entered the Monitoring Phase of Normal Mode at 1159 at EST. | | | | *** UPDATE ON 3/25/03 AT 1233 EST FROM JONATHAN SEGUNDO TO HQ OPERATIONS | | CENTER*** | | | | The Alert condition was terminated and the Station entered an Unusual Event | | at 12:31 EST due to loss of offsite power. Shutdown cooling was restored at | | 11:41 EST. Plant systems are being powered by the Emergency Diesel | | Generators. Reactor Coolant System temperature is at 104 degrees | | Fahrenheit. There are no radioactivity releases in progress. | | | | *** UPDATE ON 3/25/03 AT 1824 EST FROM AMY HAZELHOFF TO ARLON COSTA*** | | | | "Nuclear Management Company is providing additional information related to | | event notification 39699, which was reported at 1121 [1142] EST on March 25, | | 2003. This information is provided for completeness of reportability | | requirements. The event reported earlier is also reportable under the | | following criteria: | | 10CFR50.72(b)(3)(iv)(A), due to actuation of the emergency diesel generators | | and | | 10CFR50.72(b)(3)(v)(B), due to loss of shutdown cooling. | | | | "Additionally, a press release has been issued. Therefore, a report is | | required per 10CFR50.72(b)(2)(xi) for notification to offsite agencies. | | Palisades remains in an Unusual Event until a qualified offsite circuit is | | supplying a vital bus. The plant is currently stable. The root cause [of | | this incident] is not yet known." | | | | Notifications of this update were made by the Licensee to the NRC Resident | | Inspector, the state, local and other government agencies, and a press | | release was issued on this incident. | | | | * * * UPDATE ON 3/27/03 AT 1742 EST FROM PAUL ZWISSLER TO HOWIE CROUCH * * * | | | | | | Palisades Nuclear Power Plant has terminated the Unusual Event declared on | | 3/25/03. Plant vital busses are being powered by offsite power source and | | the emergency diesel generators have been secured and returned to standby | | status. There were no security implications associated with this event. | | | | The licensee has notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39705 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/27/2003| | UNIT: [1] [] [] STATE: AZ |NOTIFICATION TIME: 13:51[EST]| | RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/27/2003| +------------------------------------------------+EVENT TIME: 09:43[MST]| | NRC NOTIFIED BY: DONALD STRAKA |LAST UPDATE DATE: 03/27/2003| | HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 M/R Y 98 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM DUE TO CONDENSER TUBE RUPTURE | | | | The following information was received from the licensee via facsimile: | | | | "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 March 27, 2003, at approximately 09:43 MST Palo Verde Unit 1 experienced | | a manual reactor trip from approximately 98% rated thermal power due to a | | condenser tube rupture. Unit 1 was at normal operating temperature and | | pressure prior to the trip. All CEAs inserted fully into the reactor core. | | This was an uncomplicated reactor trip. No ESF actuations occurred and none | | were required. Safety related buses remained energized during and following | | the reactor trip. The offsite power grid is stable. No significant LCOs | | have been entered as a result of this event. There was no loss of normal | | heat removal capabilities, or loss of any safety functions associated with | | this event. No major equipment was inoperable prior to the event that | | contributed to the event. 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 event did not adversely affect the safe operation | | of the plant or the health and safety of the public. | | | | "Unit 1 is stable at normal operating temperature and pressure in Mode 3. | | There is no estimated time and date for the Unit 1 restart at the time this | | call is being made." | | | | Palo Verde Units 2 and 3 were unaffected by the Unit 1 trip. There were no | | lifts of primary or secondary power-operated or manual relief valves. Decay | | heat removal is being provided via condenser clean-up long path recirc and | | normal cooldown via the unaffected condenser. Prior to the scram, chloride | | levels in the steam generators were measured at 25 ppm and rising. Plant | | abnormal operating procedures require a manual reactor scram at 35 ppm | | chloride. There is no indications of primary-to-secondary leakage. | | | | The licensee has notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39709 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 03/28/2003| | UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 02:28[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 03/28/2003| +------------------------------------------------+EVENT TIME: [EST]| | NRC NOTIFIED BY: JIM GROOM |LAST UPDATE DATE: 03/28/2003| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N N 0 Refueling |0 Refueling | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL MEDIA INTEREST DUE TO STATE POLICE SEARCH OF THE OWNER CONTROLLED | | AREA | | | | The Calvert Control Center in Prince Frederick County received an anonymous | | call through the 911 operator which prompted the Maryland State Police to | | furnish additional officers to the site for a search of the woodline area of | | the owner controlled property. The licensee will inform their media group | | due to the potential media interest and has informed both state/local | | agencies and the NRC resident inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021