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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|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.                                     |
+------------------------------------------------------------------------------+