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Event Notification Report for June 12, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           06/11/2003 - 06/12/2003



                              ** EVENT NUMBERS **



39917  39918  39919  39920  39921  39922  39923  39924  39925  



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

|Power Reactor                                    |Event Number:   39917       |

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

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

| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 06/11/2003|

|    UNIT:  [] [2] []                 STATE:  FL |NOTIFICATION TIME: 02:26[EDT]|

|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        01:30[EDT]|

| NRC NOTIFIED BY:  JOE HESSLING                 |LAST UPDATE DATE:  06/11/2003|

|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |

|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   |

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

|                                                   |                          |

|2     A/R        Y       22       Power Operation  |0        Hot Standby      |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO HIGH HIGH STEAM GENERATOR WATER   |

| LEVEL                                                                        |

|                                                                              |

| "On 06/11/03,  Unit 2 Reactor tripped via Turbine Trip due to high-high      |

| Steam Generator level.  All Control Rods fully inserted.  Unit stable in     |

| Mode 3 (Hot Standby).  Auxiliary Feedwater system was manually started and   |

| currently maintaining steam generator levels.  Investigation is in progress  |

| to determine initial cause for loss of feed to the 2A Steam Generator from   |

| its associated low power feedwater regulating valve."                        |

|                                                                              |

|                                                                              |

| Coming out of a refueling outage reactor power was at 30% when it was        |

| noticed that main feedwater regulating valves were oscillating.  Reactor     |

| power was reduced to 20% and the low power feedwater regulating valves were  |

| placed in service so testing of the main feedwater regulating valves could   |

| be performed.  During testing of the main feedwater regulating valves at     |

| approximately 22% reactor power low power feedwater flow to the 2A Steam     |

| Generator ceased.  The dual indications for the low power feedwater          |

| regulating valve indicated that the valve was open but Steam Generator 2A    |

| water level was decreasing.  Since main feedwater regulating valve was being |

| tested the 100% bypass low power feedwater regulating valve was opened.      |

| Steam Generator water level began to increase rapidly so the valve was       |

| closed.  2A Steam Generator level began to decrease so the 100% bypass low   |

| power feedwater regulating valve was reopened.  This time 2A Steam Generator |

| water level increase above 88% narrow range which caused an automatic        |

| turbine trip. Since reactor power was greater than 15% the reactor           |

| automatically tripped due to the turbine trip. All rods fully inserted into  |

| the core.  Since the reactor core had very little decay heat the main steam  |

| isolation valves were closed and both motor driven auxiliary feedwater pumps |

| were manually started. Motor Driven Auxiliary Feedwater Pumps and  Steam     |

| Generator PORVs  operation is maintaining the plant in a Hot Standby         |

| condition.  All emergency core cooling systems are fully operable and the    |

| emergency diesel generators are fully operable if needed.  The electrical    |

| grid is stable.  The licensee believes that the stem of the low power        |

| feedwater regulating valve separated from the valve which in turn caused the |

| valve to close while still having dual indication that the low power         |

| feedwater valve was open.                                                    |

|                                                                              |

| The NRC Resident Inspector was notified of this event by the licensee.       |

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



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

|Power Reactor                                    |Event Number:   39918       |

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

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

| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 06/11/2003|

|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 13:46[EDT]|

|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        08:10[EDT]|

| NRC NOTIFIED BY:  FRANK CLIFFORD               |LAST UPDATE DATE:  06/11/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |CHRISTOPHER CAHILL   R1      |

|10 CFR SECTION:                                 |TERRY REIS           NRR     |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|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                                   

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

| INABILITY TO ACTIVATE EMERGENCY SIRENS DUE TO EQUIPMENT FAILURE              |

|                                                                              |

| "On June 11, 2003 at 0810 hours, the control room was notified that all      |

| Prompt Alert and Notification System (PANS) sirens were inoperable.  All     |

| necessary notifications to local towns and MEMA (Massachusetts Emergency     |

| Management Agency) have been made. A backup plan (route altering) is in      |

| place in the event of an emergency at Pilgrim station. It was determined     |

| that one of the sirens was transmitting a continuous radio signal to the     |

| remaining sirens, preventing actuation. The faulty siren was isolated from   |

| the system at 1125 hours."                                                   |

|                                                                              |

| The licensee informed both state and local agencies and the NRC resident     |

| inspector.                                                                   |

|                                                                              |

| This condition involving a different siren in the system occurred on         |

| 6/10/03.  See EN #39912.                                                     |

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



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

|Power Reactor                                    |Event Number:   39919       |

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

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

| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 06/11/2003|

|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 14:07[EDT]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        12:17[EDT]|

| NRC NOTIFIED BY:  GORDON ROBINSON              |LAST UPDATE DATE:  06/11/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |CHRISTOPHER CAHILL   R1      |

|10 CFR SECTION:                                 |                             |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |

|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |

|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |

|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |

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

|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          Y       100      Power Operation  |98       Power Operation  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| CONTROLLED PLANT TS SHUTDOWN DUE TO LOSS OF HVAC SYSTEM                      |

|                                                                              |

| "On 6/11/03 at 12:17, the 'A' Control Structure Chiller tripped.  The 'B'    |

| Control Structure Chiller was already inoperable for maintenance on the 'B'  |

| Chiller Fans.  With the loss of Control Structure HVAC System the ability to |

| maintain temperatures in various spaces including Relay rooms, Control Room  |

| Floor Cooling and Emergency Switchgear rooms was lost.  Units 1 and 2        |

| entered [Technical Specifications] TS 3.0.3 and a controlled shutdown of     |

| both units were commenced at 13:15.  The 'A' Chiller was restarted at 12:47  |

| and cooling was reestablished to the required areas, however the 'A' chiller |

| is not considered operable at this time.  The 'B' Chiller was placed in      |

| service and was declared operable at 13:20 [and the controlled shutdown of   |

| both units were terminated]."                                                |

|                                                                              |

| "This constitutes a Tech Spec required shutdown and requires a 4-hr ENS      |

| notification in accordance with 10 CFR 50.72(b)(2)(i).  The failure also     |

| requires an 8-hr ENS notification in accordance with 10 CFR                  |

| 50.72(b)(3)(v)(A-D) due to the loss of a safety function."                   |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

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



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

|Power Reactor                                    |Event Number:   39920       |

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

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

| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 06/11/2003|

|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 14:42[EDT]|

|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        12:45[CDT]|

| NRC NOTIFIED BY:  DON POPP                     |LAST UPDATE DATE:  06/11/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |

|10 CFR SECTION:                                 |                             |

|DDDD 73.71(b)(1)         SAFEGUARDS REPORTS     |                             |

|HFIT 26.73               FITNESS FOR DUTY       |                             |

|                                                |                             |

|                                                |                             |

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

|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          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| SECURITY REPORT INVOLVING A PLANT SECURITY OFFICER                           |

|                                                                              |

| Discovery of criminal act involving individual granted access to the site.   |

| Immediate compensatory measures taken upon discovery. The licensee informed  |

| local law enforcement and the NRC resident inspector.  Contact the           |

| Headquarters Operations Officer for additional details.                      |

|                                                                              |

| *** UPDATE ON 6/11/03 AT 2029 FROM D. POPP TO A. COSTA ***                   |

|                                                                              |

| The non-licensed employee was determined to be under the influence of        |

| alcohol during a "for cause" test.  The individual's access to all NMC       |

| facilities has been revoked.  Contact the Headquarters Operations Officer    |

| for additional details.                                                      |

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



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

|Power Reactor                                    |Event Number:   39921       |

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

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

| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 06/11/2003|

|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 14:49[EDT]|

|   RXTYPE: [1] GE-6                             |EVENT DATE:        05/22/2003|

+------------------------------------------------+EVENT TIME:        08:02[CDT]|

| NRC NOTIFIED BY:  JAMES OWENS                  |LAST UPDATE DATE:  06/11/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID GRAVES         R4      |

|10 CFR SECTION:                                 |                             |

|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|1     N          Y       100      Power Operation  |50       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| INVALID ACTUATION AND VARIOUS SYSTEM ISOLATIONS DUE TO A FAILED RELAY        |

|                                                                              |

| "On May 22, 2003, at 0802 central time, while operating at 100 percent       |

| power, Grand Gulf Nuclear Station experienced an invalid actuation of the    |

| 'B' Containment, Drywell, and Auxiliary Building Isolation System. A failed  |

| relay caused a fuse to blow which resulted in actuation of the isolation     |

| logic for the 'B' Containment, Drywell, and Auxiliary Building Isolation     |

| System. This event resulted in isolation of the Plant Service Water (PSW),   |

| Plant Chilled Water (PCW), Drywell Chilled Water (DWCW), and Instrument Air  |

| (IA) to the Auxiliary Building. The PSW isolation caused loss of Component   |

| Cooling Water (CCW) in the Auxiliary Building and loss of Turbine Building   |

| Cooling Water. Reactor power was reduced to approximately 50 percent as a    |

| result of the loss of PSW."                                                  |

|                                                                              |

| The licensee informed the NRC resident inspector.                            |

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



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

|Other Nuclear Material                           |Event Number:   39922       |

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

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

| REP ORG:  CONSOLE ENERGY INC                   |NOTIFICATION DATE: 06/11/2003|

|LICENSEE:  BUCHANAN MINE CONSOLIDATION COMPANY  |NOTIFICATION TIME: 15:12[EDT]|

|    CITY:  MAVISDALE                REGION:  2  |EVENT DATE:        06/04/2003|

|  COUNTY:                            STATE:  VA |EVENT TIME:             [EDT]|

|LICENSE#:  GENERAL               AGREEMENT:  N  |LAST UPDATE DATE:  06/11/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |MARK LESSER          R2      |

|                                                |CHRISTOPHER CAHILL   R1      |

+------------------------------------------------+FRED BROWN           NMSS    |

| NRC NOTIFIED BY:  JOE RICHARD                  |ROBERTA WARREN       IAT     |

|  HQ OPS OFFICER:  ARLON COSTA                  |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| MISSING OR LOST GAUGE CONTAINING A RADIOACTIVE SOURCE                        |

|                                                                              |

| A Texas Nuclear Product pipe mounted fixed gauge device, model 5202, Series  |

| SG, serial number B174 containing a Cesium 137 (Cs-137), 500 millicuries     |

| source (assay date of November 1984) could not be located in storage.  The   |

| gauge was removed from a pipe on the evening of  1/28/03 by an independent   |

| contractor who placed the gauge in a temporary storage on the morning of     |

| 1/29/03 at the Buchanan Mine Preparation Plant located in Mavisdale,         |

| Virginia.  The gauge was closed and pad locked before it was placed in the   |

| small building storage room.  The independent contractor and the plant       |

| foreman looked for the gauge on 6/2/03 and could not locate it.  They        |

| continued looking for the gauge until 6/4/02 when they declared that it was  |

| missing.  The licensee has no reason to believe that the gauge left the      |

| property, is retracing the steps of the gauge movement and  is interviewing  |

| their employees in an attempt to locate the gauge.                           |

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



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

|Power Reactor                                    |Event Number:   39923       |

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

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

| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 06/11/2003|

|    UNIT:  [1] [] []                 STATE:  VA |NOTIFICATION TIME: 17:18[EDT]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        14:53[EDT]|

| NRC NOTIFIED BY:  J. W. JOHNSTONE              |LAST UPDATE DATE:  06/11/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |

|10 CFR SECTION:                                 |                             |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

|                                                |                             |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|1     A/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| REACTOR PROTECTION SYSTEM  ACTUATION DUE TO MAIN TRANSFORMER LOCKOUT RELAY   |

| TURBINE TRIP                                                                 |

|                                                                              |

| "At 1453 EDT on 6/11/03, Unit 1 experience a reactor trip due to a main      |

| transformer lockout relay turbine trip.  All equipment operated as designed. |

| 10 CFR 50.72(b)(2)(iv)(B).  Main transformer 'C' appears to have an internal |

| fault, [and] may need to be replaced.  All control rods inserted fully.      |

|                                                                              |

| "A valid actuation of the Auxiliary Feedwater System resulted, due to the    |

| reactor trip. 10 CFR 50.72(b)(3)(iv)(A).  The unit is stable, using main     |

| feedwater and condenser steam dump [as a means of heat removal].             |

|                                                                              |

| All safety-related systems are available except for Unit 1 Emergency Diesel  |

| Generator which is out of service for maintenance.                           |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

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



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

|Power Reactor                                    |Event Number:   39924       |

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

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

| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 06/11/2003|

|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 18:30[EDT]|

|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        15:05[EDT]|

| NRC NOTIFIED BY:  JOHN ADDISON                 |LAST UPDATE DATE:  06/11/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |

|10 CFR SECTION:                                 |                             |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

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

|3     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE CHILLERS         |

|                                                                              |

| "At 1409 on 6/11/03, both Control Complex Chillers were declared inoperable. |

| The inoperability resulted in an entry into ITS 3.0.3 due to the inability   |

| to comply with ITS 3.7.18.  At 1505 CR-3 [Crystal River Unit 3] began a      |

| power decrease in compliance with the actions of ITS 3.0.3.  This is a       |

| 4-hour reportable event as required by 10 CFR 50.72(b)(2)(i).                |

|                                                                              |

| "At 1618 on 6/11/03 the operating Control Complex Chiller was declared       |

| Operable and the actions of ITS 3.0.3 were exited.  The plant has been       |

| returned to full power operation.                                            |

|                                                                              |

| "The safety significance of this event was small.  The Control Complex       |

| cooling safety function was available through the use of existing procedures |

| and available alternate cooling methods.  At 1456, an available Control      |

| Complex Chiller was manually loaded and is currently providing all required  |

| cooling to the control complex in automatic mode."                           |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

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



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

|Power Reactor                                    |Event Number:   39925       |

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

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

| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 06/12/2003|

|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 00:34[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        23:45[EDT]|

| NRC NOTIFIED BY:  MIKE EARLES                  |LAST UPDATE DATE:  06/12/2003|

|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |

|10 CFR SECTION:                                 |                             |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|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                                   

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

| GREATER THAN 30% OF THE OFFSITE NOTIFICATION SIRENS OUT OF SERVICE DUE TO    |

| STORM                                                                        |

|                                                                              |

| Greater than 30% of the offsite prompt notification system sirens are out of |

| service due to storm related loss of power.  Repairs are presently in        |

| progress to restore power to the affected sirens (34 of 99).  State and      |

| Local agencies have been notified to implement compensatory measures if      |

| required.                                                                    |

|                                                                              |

| The NRC Resident Inspector will be notified by the licensee.                 |

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