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Event Notification Report for October 3, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/02/2002 - 10/03/2002

                              ** EVENT NUMBERS **

39238   39239   39240   39241   39242

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|  POWER REACTOR 	                         EN NUMBER:39238   |
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LICENSEE: FIRSTENERGY NUCLEAR OPERATING COMPANY
SITE: DAVIS BESSE 1                         EN NUMBER:39238
DOCKET: 05000346                         EVENT DATE: 10-02-02
RX TYPE: PWR                             EVENT TIME: 13:44
VENDORS: B&W-R-LP                       NOTIFY DATE: 10-02-02
EMERGENCY CLASS: N/A  REGION: 3 STATE: OH      TIME: 14:20
OPS OFFICER: MIKE NORRIS              
10 CFR SECTION: APRE  OFFSITE NOTIFICATION                     
                DDDD  SAFEGUARDS REPORTS                       
UNIT  SCRAM   RX   INIT  INITIAL MODE     CURR   CURRENT MODE
      CODE   CRIT  PWR                    PWR
 1    N       N      0   Refueling          0   Refueling      

1 HOUR SAFEGUARDS REPORT                                         
                                                                 
Attempted introduction of contraband into controlled access area.
                                                                 
                                                                 
The NRC Resident Inspector was notified.                         
                                                                 
Contact Headquarters Operations Officer for additional details.  

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|  POWER REACTOR 	                         EN NUMBER:39239   |
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LICENSEE: DETROIT EDISON CO.                 
SITE: FERMI 2                               EN NUMBER:39239
DOCKET: 05000341                         EVENT DATE: 10-02-02
RX TYPE: BWR                             EVENT TIME: 14:53
VENDORS: GE-4                           NOTIFY DATE: 10-02-02
EMERGENCY CLASS: N/A  REGION: 3 STATE: MI      TIME: 17:24
OPS OFFICER: MIKE NORRIS              
10 CFR SECTION: AESF  VALID SPECIF SYS ACTUATION               
                ARPS  RPS ACTUATION - CRITICAL                 
UNIT  SCRAM   RX   INIT  INITIAL MODE     CURR   CURRENT MODE
      CODE   CRIT  PWR                    PWR
 2    A/R     Y    100   Power Operation    0   Hot Shutdown   

REACTOR SCRAM DUE TO TURBINE TRIP FROM A LOSS OF CONDENSER VACUUM
                                                                 
"On Wednesday, October 2, 2002 at 1453 hours, the reactor        
scrammed from 100% power. Condenser vacuum was lost when         
circulating pump No. 2 failed.  Condenser pressure went above the
turbine trip setpoint.  The main turbine, tripped and the reactor
scrammed.   All rods fully inserted.                             
                                                                 
"Reactor level is stable in the normal band (197 inches).        
Reactor Level 3 (173 inches) was reached and level was restored  
to normal.                                                       
                                                                 
"No ECCS systems actuated. No safety/relief valves opened.  All  
systems functioned normally.   Reactor level is being maintained 
using one reactor feed pump through the startup level control    
valve.   Cool down is through the main turbine bypass valves to  
the main condenser.   The following 'Level 3' isolations occurred
as expected:                                                     
Group 4 - RHR Shutdown Cooling and Head Spray                    
Group 13 - Drywell Sumps                                         
Group 15 - Traversing Incore Probe Systems                       
                                                                 
"NRC Senior Resident Inspector has been notified.                
                                                                 
"This report is being made in accordance with 10 CFR             
50.72(b)(2)(iv)(B), Any event that results in actuation of the   
reactor protection system (RPS) when the reactor is critical, and
10 CFR 50.72(b)(3)(iv)(A), Specified System Actuation."          

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|  POWER REACTOR 	                         EN NUMBER:39240   |
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LICENSEE: ENERGY NORTHWEST                   
SITE: COLUMBIA GENERATING STATION 2         EN NUMBER:39240
DOCKET: 05000397                         EVENT DATE: 09-26-02
RX TYPE: BWR                             EVENT TIME:      
VENDORS: GE-5                           NOTIFY DATE: 10-02-02
EMERGENCY CLASS: N/A  REGION: 4 STATE: WA      TIME: 17:58
OPS OFFICER: MIKE NORRIS              
10 CFR SECTION: NONR  OTHER UNSPEC REQMNT                      
UNIT  SCRAM   RX   INIT  INITIAL MODE     CURR   CURRENT MODE
      CODE   CRIT  PWR                    PWR
 2    N       Y    100   Power Operation  100   Power Operation

24 HOUR CONDITION OF LICENSE REPORT                              
                                                                 
The following is a facsimile received from the Region 4 Duty     
Officer.                                                         
                                                                 
"This facsimile is being sent to confirm a telephonic report of  
October 1, 2002 that was made pursuant to the Columbia Generating
Station Operating License (NPF-21) condition 2.F, which states:  
                                                                 
'With the exception of 2.C(2) the licensee shall report any      
violations of the requirements contained in Section 2.C, and E of
this license within 24 hours by telephone and confirm by         
telegram, mailgram, or facsimile transmission to the NRC Regional
Administrator, Region V or that administrator's designee, no     
later than the first working day following the violation, with a 
written followup report within 14 days.                          
                                                                 
'The subject of the report is the discovery that all the         
provisions of the Commission-approved physical security plan were
not maintained in effect for a period of approximately 2 hours on
September 26, 2002 when personnel gates to the independent Spent 
Fuel Storage Installation (ISFSI) protected area were unlocked,  
open, and unattended. During this time, the operable ISFSI       
intrusion detection system did nor detect any entry into the     
ISFSI protected area. A written follow-up report regarding this  
issue will be submitted on or before October 15, 2002.'          

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|  POWER REACTOR 	                         EN NUMBER:39241   |
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LICENSEE: PPL SUSQUEHANNA LLC                
SITE: SUSQUEHANNA 1 2                       EN NUMBER:39241
DOCKET: 05000387 05000388                EVENT DATE: 10-03-02
RX TYPE: BWR BWR                         EVENT TIME: 03:15
VENDORS: GE-4 GE-4                      NOTIFY DATE: 10-03-02
EMERGENCY CLASS: UNU  REGION: 1 STATE: PA      TIME: 03:33
OPS OFFICER: JOHN MacKINNON           
10 CFR SECTION: AAEC  EMERGENCY DECLARED                       
UNIT  SCRAM   RX   INIT  INITIAL MODE     CURR   CURRENT MODE
      CODE   CRIT  PWR                    PWR
 1    N       Y    100   Power Operation  100   Power Operation
 2    M/R     Y      1   Startup            0   Hot Shutdown   

UNUSUAL EVENT DECLARED PER EAL 14.1- FIRE LASTING GREATER THAN 15
MINUTES & ACTIVATION OF THE FIRE BRIGADE.                        
                                                                 
"At 0230 on 10/3/02, the control room was notified that there was
a fire at Startup Transformer T-20. Unit 2 was in the process of 
starting up and was at a pressure of 435 psig and range 8 on the 
IRMs.  T-20 lost power which caused the recirc pumps on Unit 2 to
trip.  With no recirculation, operators placed the mode switch to
shutdown.  All rods were inserted. Unit 1 was at 100% power at   
the time and continued to operate.  The Station Fire Brigade was 
activated.  The deluge system extinguished the fire in 10        
minutes"                                                         
                                                                 
Non-Vital power is being supplied to T-20 Startup Transformer Bus
from Startup Transformer T-10 via cross tie breaker.  Offsite    
fire department was called but was not needed.  All Emergency    
Core Cooling systems and the Emergency Diesel Generators are     
fully operable if needed.                                        
                                                                 
The Unusual event will be terminated after an assessment of what 
caused the Startup Transformer T-20 fire/failure.                
                                                                 
                                                                 
The licensee notified the State of PA, surrounding counties and  
the NRC Resident Inspector of the declaration of an Unusual      
Event.                                                           
                                                                 
***UPDATE  ON 10/03/02 AT 0605ET BY SID MORGAN  TAKEN BY         
MACKINNON ***                                                    
                                                                 
EAL 14.1 was exited and the Unusual Event terminated at 05:52 ET.
Unusual event was terminated after damage assessment of Startup  
Transformer T-20  was completed.  R1DO (Pete Esselgroth), NRR EO 
(Bill Dean) & FEMA (Sweetser)  notified.                         
                                                                 
The NRC Resident Inspector was notified of the termination of the
Unusual event by the licensee.                                   

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|  POWER REACTOR 	                         EN NUMBER:39242   |
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LICENSEE: PPL SUSQUEHANNA LLC                
SITE: SUSQUEHANNA 2                         EN NUMBER:39242
DOCKET:  05000388                        EVENT DATE: 10-03-02
RX TYPE:  BWR                            EVENT TIME: 02:30
VENDORS:  GE-4                          NOTIFY DATE: 10-03-02
EMERGENCY CLASS: N/A  REGION: 1 STATE: PA      TIME: 05:15
OPS OFFICER: JOHN MacKINNON           
10 CFR SECTION: ASHU  PLANT S/D REQD BY TS                     
                ARPS  RPS ACTUATION - CRITICAL                 
UNIT  SCRAM   RX   INIT  INITIAL MODE     CURR   CURRENT MODE
      CODE   CRIT  PWR                    PWR
 2    M/R     Y      1   Startup            0   Hot Shutdown   

MANUAL REACTOR SCRAM DUE TO LOSS OF POWER TO RECIRC PUMPS.       
                                                                 
"At 0230 on 01/3/02, the control room was notified that there was
a fire at Startup Transformer T-20.  Unit 2 was in the process of
starting up and was at a pressure of 435 psig and range 8 on the 
IRMs.  T-20 lost power which caused the recirc pumps on Unit 2 to
trip.  With no recalculation while in Mode 2, Tech Specs requires
the unit to be in Mode 3 within 12 hours.  Operations placed the 
mode switch to shutdown.  All rods were inserted.  Unit 1 was at 
100% power at the time and continued to operate.  The Station    
Fire Brigade was activated.  The deluge system extinguished the  
fire  in 10 minutes.  An Unusual Event was declared under EAL    
14.1 at 03:15.                                                   
                                                                 
"This is a 4 hr Non-Emergency notification under 10 CFR          
50.72(b)(2)(I) for a Tech Spec required shutdown and a 4 hr      
Non-Emergency notification under 10 CFR 50.72(b)(2)(iv)(B) for an
RPS actuation."                                                  
                                                                 
A press release will be made.                                    
                                                                 
The NRC Resident Inspector was notified of this event by the     
licensee.