The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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