U.S. Nuclear Regulatory Commission
                             Operations Center
 
                             Event Reports For
                            08/22/94 - 08/23/94
 
                             ** EVENT NUMBERS **
 
27694  27695  

+----------------------------------+              +-----------------------+     
|POWER REACTOR                     |              |EVENT NUMBER:  27694   |     
+----------------------------------+              +-----------------------+     
+------------------------------------------------+-----------------------------+
|FACILITY: LIMERICK                   REGION:  1 |NOTIFICATION DATE: 08/22/94  |
|UNIT:     [1] [ ] [ ]                 STATE: PA |NOTIFICATION TIME: 14:04 [ET]|
|RX TYPE: [1] GE-4,[2] GE-4                      |EVENT DATE:        08/22/94  |
+------------------------------------------------+EVENT TIME:        12:20[EDT]|
|NRC NOTIFIED BY: ROBERT DELANEY                 |LAST UPDATE DATE:  08/22/94  |
|HQ OPS OFFICER:  DOUG WEAVER                    +-----------------------------+
+------------------------------------------------+       NOTIFICATIONS         |
|EMERGENCY CLASS: NOT APPLICABLE                
+-----------------------------+
|10 CFR SECTION:                                 |JOHN KINNEMAN         RDO   
|
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                            
|
|                                                |                            
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|                                                |                            
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|                                                |                            
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|                                                |                            
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+-----+----------+-------+--------+--------------+--+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| FAILURE OF CHANNEL D OF THE REACTOR ENCLOSURE VENTILATION EXHAUST RADIATION 
|
| MONITORING SYSTEM CAUSED A GROUP 6C ESF ISOLATION.                          
|
|                                                                             
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| "AT 1220 EDT, THE UNIT 1, D CHANNEL OF THE REACTOR ENCLOSURE VENTILATION    
|
| EXHAUST RADIATION MONITORING SYSTEM (RISH-026-1K609D) TRIPPED AND CAUSED A  
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| GROUP 6C ISOLATION.  IT WAS VERIFIED THAT NO HIGH RADIATION CONDITION       
|
| EXISTED AND NO INCREASE WAS IN PROGRESS.  NO TESTING OR MANIPULATIONS WERE  
|
| BEING PERFORMED.  SYSTEMS AFFECTED BY THE ISOLATION WERE THE PRIMARY        
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| CONTAINMENT SAMPLE, POST LOCA RECOMBINERS, REACTOR RECIRCULATING PUMP SEAL  
|
| PURGE, PRIMARY CONTAINMENT INSTRUMENT GAS BARRIER BLOCK AND VENTS AND       
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| NITROGEN MAKE-UP BARRIER BLOCK AND VENTS.  DURING THE INVESTIGATION, THE    
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| RISH-026-1K609D WAS FOUND TO BE CAUSING AN INOP TRIP WHICH SUBSEQUENTLY     
|
| RESET.  THE RADIATION MONITOR INDICATES NORMAL, AND PLANT STAFF ARE         
|
| INVESTIGATING THE POSSIBLE CAUSE."                                          
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|                                                                             
|
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                           
|
+------------------------------------------------------------------------------+

+----------------------------------+              +-----------------------+    

|POWER REACTOR                     |              |EVENT NUMBER:  27695   |    

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

+------------------------------------------------+-----------------------------+
|FACILITY: FERMI                      REGION:  3 |NOTIFICATION DATE: 08/22/94 
|
|UNIT:     [2] [ ] [ ]                 STATE: MI |NOTIFICATION TIME: 18:46
[ET]|
|RX TYPE: [2] GE-4                               |EVENT DATE:        08/22/94 
|
+------------------------------------------------+EVENT TIME:       
17:10[EDT]|
|NRC NOTIFIED BY: BOB GAILLIEZ                   |LAST UPDATE DATE:  08/22/94 
|
|HQ OPS OFFICER:  DOUG WEAVER                   
+-----------------------------+
+------------------------------------------------+       NOTIFICATIONS        
|
|EMERGENCY CLASS: NOT APPLICABLE                
+-----------------------------+
|10 CFR SECTION:                                 |MIKE MCCANN           RDO   
|
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                            
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|                                                |                            
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|                                                |                            
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|                                                |                            
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|                                                |                            
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+-----+----------+-------+--------+--------------+--+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|  INIT RX MODE   |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|  2  |   N          N        0     REFUELING       |     0    REFUELING      
|
|     |                                             |                         
|
|     |                                             |                         
|
+-----+---------------------------------------------+--------------------------+

                                   EVENT TEXT
+------------------------------------------------------------------------------+
| ISOLATION VALVE WILL NOT FUNCTION UNDER ACCIDENT CONDITIONS.                
|
|                                                                             
|
| DURING ENGINEERING REVIEW OF THE DESIGN OF THE REACTOR RECIRCULATION PUMP   
|
| SEAL PURGE LINE AIR OPERATED ISOLATION VALVES, IT WAS DISCOVERED THAT THE   
|
| LINE WILL NOT BE PROPERLY ISOLATED UNDER ACCIDENT CONDITIONS.  THESE VALVES 
|
| HAVE INADEQUATE CLOSING FORCE TO SHUT THE VALVES DURING ACCIDENT            
|
| CONDITIONS.                                                                 
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|                                                                             
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| THE ENGINEERING DEPARTMENT IS STILL INVESTIGATING POSSIBLE SOLUTIONS TO THE 
|
| PROBLEM.                                                                    
|
|                                                                             
|
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                        
|
+------------------------------------------------------------------------------+