Event Notification Report for February 11, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/08/2002 - 02/11/2002

                              ** EVENT NUMBERS **

38676  38679  38683  38684  38685  38686  38687  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

Power Reactor                                    Event Number:   38676       

                         
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 FACILITY: LIMERICK                 REGION:  1  NOTIFICATION DATE: 02/06/2002
    UNIT:  [1] [] []                 STATE:  PA NOTIFICATION TIME: 22:37[EST]
   RXTYPE: [1] GE-4,[2] GE-4                    EVENT DATE:        02/06/2002

 NRC NOTIFIED BY:  PETE ORPHANOS                LAST UPDATE DATE:  02/08/2002
 

EMERGENCY CLASS:          NON EMERGENCY         LAWRENCE DOERFLEIN   R1      
10 CFR SECTION:                                                              
AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION                                 
                                                                             
                                                                             
                                                                             

UNIT SCRAM CODERX CRITINIT PWR   INIT RX MODE  CURR PWR  CURR RX MODE   

1     N          Y       94       Power Operation  94       Power Operation  
                                                                             
                                                                             

                                   EVENT TEXT                                   

 HPCI DECLARED INOPERABLE                                                     
                                                                              
 "During the completion of scheduled testing on the Unit 1 High Pressure      
 Coolant injection (HPCI) system, a valve designed to provide minimum flow    
 protection for the associated pump did not automatically open in the time    
 frame expected during pump shutdown. The valve did respond correctly to      
 Operator action.                                                             
                                                                              
 "HPCI was declared inoperable as of 1722 hours on February 6th, 2002.        
 Troubleshooting on the minimum flow protection circuitry is currently in     
 progress.                                                                    
                                                                              
 "This report is being made in pursuant to 10CFR50.72(b)(3)(V)(D) for failure 
 of a single train accident mitigation system."                               
                                                                              
 The NRC resident inspector has been informed of this event by the licensee.  
                                                                              
 * * * UPDATE 1508EST ON 2/8/02 FROM STAN GAMBLE TO S. SANDIN * * *           
                                                                              
 The licensee is retracting this report based on the following:               
                                                                              
 "This is a retraction of the event notification made on 2/6/02 at 22:37      
 hours. This event (#38676) was initially reported as a safety system         
 functional failure under the requirement of 10CFR50.72(b)(3)(v)(D), after    
 the Unit 1 High Pressure Coolant Injection (HPCI) minimum flow valve did not 
 automatically open during system testing.                                    
                                                                              
 "Subsequent testing verified that the valve would have opened automatically  
 without operator action following the low flow alarm actuation. A delay in   
 response is expected when system flow is reduced to a value within the range 
 of the flow transmitter. This delay in response, and the short duration of   
 pump operation at a no flow condition is not detrimental to the HPCI pump.   
                                                                              
 "The system response was verified to be as designed considering the test     
 conditions. A condition did not exist at the time of discovery that could    
 have prevented the fulfillment of the safety function."                      
                                                                              
 The licensee informed the NRC Resident Inspector.  Notified R1DO(Doerflein). 

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

Power Reactor                                    Event Number:   38679       

                         
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 FACILITY: FITZPATRICK              REGION:  1  NOTIFICATION DATE: 02/07/2002
    UNIT:  [1] [] []                 STATE:  NY NOTIFICATION TIME: 14:26[EST]
   RXTYPE: [1] GE-4                             EVENT DATE:        02/07/2002

 NRC NOTIFIED BY:  SHAWN ALLEN                  LAST UPDATE DATE:  02/08/2002
 

EMERGENCY CLASS:          NON EMERGENCY         LAWRENCE DOERFLEIN   R1      
10 CFR SECTION:                                                              
AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION                                 
                                                                             
                                                                             
                                                                             

UNIT SCRAM CODERX CRITINIT PWR   INIT RX MODE  CURR PWR  CURR RX MODE   

1     N          Y       100      Power Operation  100      Power Operation  
                                                                             
                                                                             

                                   EVENT TEXT                                   

 HPCI DECLARED INOPERABLE FOLLOWING DISCOVERY OF UNKNOWN CONTAMINANT
IN OIL   
                                                                              
 "Declared High Pressure Coolant Injection System (HPCI) INOP due to unknown  
 contaminants in the oil system.  Plant formulated an action plan to resample 
 the sump, identify the particles, and identify the source of the             
 contaminants.  Entered 7 day LCO per Tech Spec 3.5.C.1.a."                   
                                                                              
 The licensee informed the NRC Resident Inspector.                            
                                                                              
 * * * UPDATE 1620EST ON 2/8/02 FROM ANDY HALLIDAY TO S. SANDIN * * *         
                                                                              
 The licensee is retracting this report based on the following:               
                                                                              
 "Further analysis has shown that the foreign material found in the HPCI lube 
 oil sample taken 2/7/2002 did not cause HPCI to become inoperable, it could  
 have performed its design function before, during and after the time it was  
 declared inoperable.                                                         
                                                                              
 "This is based on determination through engineering review that the type and 
 size of material found in the sample would not have prevented any part of    
 HPCI from failing to operate as required.                                    
                                                                              
 "Preliminary cause determination is that 4 liters of unfiltered oil were     
 added to the 150 gallon lube oil system during the previous monthly sample   
 evolution.                                                                   
                                                                              
 "For these reasons. JAF is concluding that HPCI remained operable from the   
 original LCO entry of 12:15; 2/7/02. and is retracting notification          
 #38679."                                                                     
                                                                              
 The licensee informed the NRC Resident Inspector.  Notified R1DO(Doerflein). 



General Information or Other                     Event Number:   38683       

                         
-

 REP ORG:  OHIO BUREAU OF RADIATION PROTECTION  NOTIFICATION DATE:
02/08/2002
LICENSEE:  BATTELLE MEMORIAL INSTITUTE          NOTIFICATION TIME: 13:43[EST]
    CITY:  COLUMBUS                 REGION:  3  EVENT DATE:        01/29/2002
  COUNTY:                            STATE:  OH EVENT TIME:             [EST]
LICENSE#:  OH03610250000         AGREEMENT:  Y  LAST UPDATE DATE:  02/08/2002
  DOCKET:                                      
                                                PERSON          ORGANIZATION 
                                                THOMAS KOZAK         R3      
                                                FRED BROWN           NMSS    

 NRC NOTIFIED BY:  MICHAEL SNEE                                              
  HQ OPS OFFICER:  JOHN MacKINNON                                            

EMERGENCY CLASS:          NON EMERGENCY                                      
10 CFR SECTION:                                                              
NAGR                     AGREEMENT STATE                                     
                                                                             
                                                                             
                                                                             
                                                                             


                                   EVENT TEXT                                   

 AGREEMENT STATE EVENT                                                        
                                                                              
 The licensee reported the loss of a internally contaminated duct.  The duct  
 is 13-feet long and 4-inches in diameter and contaminated with U-234, U-235, 
 and U-238, with the highest concentration being U-234.  The licensee         
 estimates that 1.5 microcuries of U-234 is in the duct.  The duct was sent   
 to a construction debris landfill in Franklin County, Ohio along with other  
 construction debris.                                                         
                                                                              
 Source/Material:  Unsealed Material, Other                                   
 Radionuclide:  U-234                                                         
 Activity (Curies):  0.0000015                                                
                                                                              
 Agreement State Item number:  OH-02-021                                      



General Information or Other                     Event Number:   38684       

                         
-

 REP ORG:  MARYLAND DEPT OF THE ENVIRONMENT     NOTIFICATION DATE:
02/08/2002
LICENSEE:  HOLY CROSS HOSPITAL                  NOTIFICATION TIME: 15:36[EST]
    CITY:  SILVER SPRINGS           REGION:  1  EVENT DATE:        02/04/2002
  COUNTY:  MONTGOMERY                STATE:  MD EVENT TIME:        15:00[EST]
LICENSE#:  MD-31-001-01          AGREEMENT:  Y  LAST UPDATE DATE:  02/08/2002
  DOCKET:                                      
                                                PERSON          ORGANIZATION 
                                                LAWRENCE DOERFLEIN   R1      
                                                PAUL FREDRICKSON     R2      

 NRC NOTIFIED BY:  RAY MANLEY                                                
  HQ OPS OFFICER:  STEVE SANDIN                                              

EMERGENCY CLASS:          NON EMERGENCY                                      
10 CFR SECTION:                                                              
NAGR                     AGREEMENT STATE                                     
                                                                             
                                                                             
                                                                             
                                                                             


                                   EVENT TEXT                                   

 AGREEMENT STATE REPORT INVOLVING POTENTIAL PERSONNEL EXPOSURES            
  
                                                                              
 On 2/4/02 at 1500EST a female patient undergoing treatment for thyroid       
 cancer received 250 millicuries I-131 at the Holy Cross Hospital located at  
 1500 Forest Glen Road in Silver Springs, MD 20910.  The patient subsequently 
 expired on 2/5/02 at 0630EST.  The body was released by the hospital to the  
 Metropolitan Funeral Home located at 5517 Vine Street in Alexandria, VA for  
 cremation.  Due to the relatively short period of time between               
 administration of the I-131 dose and the patient's demise radiation levels   
 were measured 67 mR/hr @ 1 meter.  The decedent was transferred back to Holy 
 Cross Hospital and is in an area away from the general public awaiting final 
 disposition.  Both NRC Region I (Duncan White) and NRC Region II are aware   
 of this event.  Contamination surveys were performed at the Funeral Home     
 with negative results.  An investigation is ongoing to determine any         
 personnel exposures associated with this incident.                           



Other Nuclear Material                           Event Number:   38685       

                         
-

 REP ORG:  BRIGHAM YOUNG UNIVERSITY             NOTIFICATION DATE: 02/08/2002
LICENSEE:  BRIGHAM YOUNG UNIVERSITY             NOTIFICATION TIME: 16:15[EST]
    CITY:  LAIE                     REGION:  4  EVENT DATE:        01/01/2002
  COUNTY:  HONOLUL                   STATE:  HI EVENT TIME:             [HST]
LICENSE#:                        AGREEMENT:  N  LAST UPDATE DATE:  02/08/2002
  DOCKET:                                      
                                                PERSON          ORGANIZATION 
                                                JOHN PELLET          R4      
                                                M. WAYNE HODGES      NMSS    

 NRC NOTIFIED BY:  JIM FREEMAN                                               
  HQ OPS OFFICER:  STEVE SANDIN                                              

EMERGENCY CLASS:          NON EMERGENCY                                      
10 CFR SECTION:                                                              
BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X                               
                                                                             
                                                                             
                                                                             
                                                                             


                                   EVENT TEXT                                   

 SELF-POWERED TRITIUM EXIT SIGNS DISCOVERED MISSING FOLLOWING FACILITY      
 
 RENOVATION                                                                   
                                                                              
 The auditorium at the Brigham Young University Campus in Laie, HI underwent  
 renovation between 6/2000 and 1/2002.  The contractor removed nine (9)       
 self-powered tritium exit signs for storage and reinstallation following     
 completion of the work.  After work was completed the signs could not be     
 located.  The Safety Officer (SO) at the University believes that the signs  
 may have been installed at another business location.  Based on other        
 self-powered exit signs currently in possession, the SO feels the missing    
 signs contained 10 Curie tritium sources each and were manufactured by SRB   
 Technologies, Inc. located in Winston-Salem, NC between 1992 and 1993.  A    
 written report will be submitted for the loss of this general licensed       
 material in accordance with NUREG-1556.                                      



Power Reactor                                    Event Number:   38686       

                         
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 FACILITY: HATCH                    REGION:  2  NOTIFICATION DATE: 02/09/2002
    UNIT:  [1] [] []                 STATE:  GA NOTIFICATION TIME: 00:30[EST]
   RXTYPE: [1] GE-4,[2] GE-4                    EVENT DATE:        02/08/2002

 NRC NOTIFIED BY:  ED BURKETT                   LAST UPDATE DATE:  02/09/2002
 

EMERGENCY CLASS:          NON EMERGENCY         PAUL FREDRICKSON     R2      
10 CFR SECTION:                                                              
ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA                             
                                                                             
                                                                             
                                                                             

UNIT SCRAM CODERX CRITINIT PWR   INIT RX MODE  CURR PWR  CURR RX MODE   

1     M/R        Y       27       Power Operation  0        Hot Shutdown     
                                                                             
                                                                             

                                   EVENT TEXT                                   

 MANUAL REACTOR SCRAM - DEGRADED VACUUM DUE TO ACTIONS FOR HIGH
OFFGAS        
 HYDROGEN                                                                     
                                                                              
 "Plant Hatch Unit 1 was SCRAMMED at 2252 EST on 02-08-2002. The Reactor was  
 SCRAMMED from approximately 27% RTP and the Main Turbine subsequently        
 tripped. Degraded function of the Main Condenser Offgas Recombiner system    
 had resulted in high Hydrogen in the Offgas. The  'Failure of Recombiner'    
 Abnormal Operating procedure (AOP) had been entered at approximately 2100    
 and a power reduction begun from 100% RTP at about 2105. Per the AOP, the    
 inservice Steam jet Air Ejector was removed from service at 2220 (due to the 
 Offgas Hydrogen concentration reaching approximately 4%). Hatch Unit 1 was   
 subsequently scrammed due to degrading Condenser Vacuum. The mechanical      
 vacuum pump was placed in service after the SCRAM to maintain Condenser      
 Vacuum as the heat sink. The lowest Reactor Water Level noted during the     
 SCRAM (approximately 7" above Instrument zero) was above any ESF actuation   
 settings, so no ESFs were required or received. No Reactor Pressure increase 
 was noted during the SCRAM. At this time plans are to proceed to Cold        
 Shutdown for repairs to the Offgas Recombiner system and other maintenance.  
 Air purge had been placed inservice to purge the Hydrogen from the Offgas    
 system at around 2230, and remains inservice to reduce Hydrogen              
 concentrations."                                                             
                                                                              
 The licensee notified the NRC Resident Inspector.                            



Power Reactor                                    Event Number:   38687       


 FACILITY: DIABLO CANYON            REGION:  4  NOTIFICATION DATE: 02/09/2002
    UNIT:  [] [2] []                 STATE:  CA NOTIFICATION TIME: 10:09[EST]
   RXTYPE: [1] W-4-LP,[2] W-4-LP                EVENT DATE:        02/09/2002

 NRC NOTIFIED BY:  DOUGLAS DYE                  LAST UPDATE DATE:  02/09/2002
 

EMERGENCY CLASS:          NON EMERGENCY         JOHN PELLET          R4      
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 CODERX CRITINIT PWR   INIT RX MODE  CURR PWR  CURR RX MODE   

                                                                             
2     M/R        Y       100      Power Operation  0        Hot Standby      
                                                                             

                                   EVENT TEXT                                   

 MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER TO A STEAM GENERATOR        
   
                                                                              
 "At 0337, on 2/9/2002, Unit 2 reactor was manually tripped due to a failure  
 of feedwater regulating valve FW-2-FCV-540.  The valve failed closed         
 isolating feedwater to steam generator 2-4.  The reason for the failure is   
 currently unknown, investigation continues.  All safety systems responded as 
 required. [All control rods fully inserted]. Auxiliary feedwater pumps 2-1,  
 2-2, 2-3 started as required in response to low steam generator water        
 levels.                                                                      
                                                                              
 "DCPP unit 2 is stable in Mode 3, heat removal is via steam dumping to the   
 normal condenser, auxiliary feedwater continues to supply the steam          
 generators."  The unit will remain in Mode 3 until repairs are made.         
                                                                              
 The unit 2 steam generator 4 has had a long term tube leak (about 2 years)   
 on the order of about 3.82 gpd (TS limit 150 gpd) by most recent             
 calculation.  Secondary activity is less than detectable and only a count    
 rate on steam jet air ejector is positive indication.  Primary activity      
 pretrip was 3.47E-3 �Ci/ml.                                                  
                                                                              
 The licensee notified the NRC Resident Inspector and will make a normal      
 press release.                                                               



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