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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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|Power Reactor                                    |Event Number:   39558       |

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| 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  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| 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).                                                    |

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|Power Reactor                                    |Event Number:   39699       |

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| 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                                   

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| 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.                        |

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+------------------------------------------------------------------------------+

|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                                   

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| 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.                        |

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+------------------------------------------------------------------------------+

|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                                   

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| 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.                                     |

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