Headquarters Daily Report

                         JUNE 07, 1996

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                    REPORT             NEGATIVE            NO INPUT
                    ATTACHED           INPUT RECEIVED      RECEIVED

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REGION II                              û                   
REGION III                             û                   
REGION IV           û                                      
PRIORITY ATTENTION REQUIRED  MORNING REPORT - REGION IV  JUNE  7, 1996

Licensee/Facility:                     Notification:

Entergy Operations, Inc.               MR Number: 4-96-0053
River Bend 1                           Date: 06/07/96
St Francisville,Louisiana              Notified by Resident Inspector     
Dockets: 50-458
BWR/GE-6                              

Subject: ELECTROHYDRALIC CONTROL SYSTEM TROUBLES CAUSE REACTOR SCRAM     

Discussion:

On June 6, 1996, at 6:11 p.m. (CDT), after receipt of an upscale average 
power range monitor alarm (at 108 percent), operators immediately        
inserted a manual reactor scram from 108 percent power in response to    
increasing reactor power.  All rods inserted and all safety systems      
responded as required.  No ESF actuations were received.  The plant is   
stable in Mode 3 (Hot Shutdown) at 940 psig.                             
                                                                         
At approximately 6:09 p.m. all four combined intercept valves (CIV),     
which isolate steam to the low pressure turbines, closed for unknown     
reasons.  Shortly, after the CIVs closed, Turbine Stop Valve 2 closed,   
isolating one of the main steam lines to the high pressure turbine.  The 
turbine bypass control valves opened because of the high pressure        
condition in the main steam systems.  These events caused all four       
moisture separator reheaters (MSR) relief valves to lift.  When the MSR  
relief valves lifted, steam system pressure decreased and the turbine    
control valves began to close.  As the turbine control valves closed, the
MSR relief valves reseated causing a pressure spike and a reactor power  
increase.  Following the scram, reactor water level decreased to below   
Level III (i.e., the reactor scram hotpoint).  Operators entered the     
emergency operating procedures, and recovered reactor water level with   
the reactor feed pumps.  No ESF actuations were received.                
                                                                         
The licensee initiated an event review team to determine the sequence of 
events, root cause, and safety significance.  The licensee believes that 
the transient resulted from problems in the electrohydraulic control     
system.                                                                  
                                                                         
The licensee plans a two day forced outage to clear blockage in the      
drywell floor drain sumps, complete repairs on the Division II diesel    
generator, and complete repairs on the Division II control room air      
conditioning system.  At the time of the event, the licensee was already 
in the limiting conditions for operation to perform corrective           
maintenance.                                                             

Regional Action:

The resident inspectors responded to the site and monitored the          
licnesee's response.  The resident inspectors are following up on the    
SERT's investigation.                                                    

Contact:  D. Proulx                  (504)635-3193
          G. Pick                    (817)860-8270
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REGION IV  MORNING REPORT     PAGE  2          JUNE  7, 1996

Licensee/Facility:                     Notification:

Wolf Creek Nuclear Oper. Corp.         MR Number: 4-96-0054
Wolf Creek 1                           Date: 06/06/96
Burlington,Kansas                      Senior Resident Inspector          
Dockets: 50-482
PWR/W-4-LP                            

Subject: REACTOR TRIPPED FROM 100 PERCENT DUE TO FEED REGULATING VALVE   
         FAILING CLOSED (REPORTABLE EVENT 30590)                         


Discussion:

An automatic reactor trip occurred at 1:18 p.m. (CDT) on June 6, 1996, on
low low level in Steam Generator 3.  Feedwater Regulating Valve (FRV) C  
closed, which caused loss of feedwater flow to the steam generator.  The 
low low level caused the reactor trip and an automatic turbine trip.  All
control rods inserted completely, steam was dumped to the main condenser,
main feedwater system isolated and auxiliary feedwater system actuated,  
as designed.  The plant remained stable in Mode 3.                       
                                                                         
The plug of the FRV had separated from the valve stem due to failure of  
the rolled pin installed to hold the valve plug on the stem.  This       
problem had been identified previously on FRV A, which had been corrected
by replacing the rolled pin with a solid pin that is peened in place. The
licensee plans to replace the rolled pins with solid pins in FRV B, C and
D prior to starting up.  Plant startup is scheduled for 8 p.m. on June 7,
1996, with return to the grid scheduled for 2 a.m. on June 8, 1996.      

Regional Action:

Resident Inspectors are monitoring the licensee's activities.            

Contact:  J. F. Ringwald             (316)364-8653
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