Headquarters Daily Report

                         AUGUST 13, 1997

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                    REPORT             NEGATIVE            NO INPUT
                    ATTACHED           INPUT RECEIVED      RECEIVED

HEADQUARTERS                           û                   
REGION I                               û                   
REGION II                              û                   
REGION III                             û                   
REGION IV           û                                      
PRIORITY ATTENTION REQUIRED  MORNING REPORT - REGION IV  AUGUST 13, 1997

Licensee/Facility:                     Notification:

Omaha Public Power District            MR Number: 4-97-0064
Ft Calhoun 1                           Date: 08/13/97
Fort Calhoun,Nebraska                  SRI via telephone                  
Dockets: 50-285
PWR/CE                                

Subject: REDUCTION IN POWER DUE TO INOPERABLE REACTOR PROTECTION SYSTEM  
         CHANNELS                                                        


Discussion:

At approximately 5 p.m. (CDT) on August 12, 1997, the licensee           
determined, during a review of the shape annealing factor test results,  
that the flux shape annealing factors measured during the startup for the
current operating cycle (November 1996) were larger than the values      
currently installed in the reactor protection system.  This difference   
resulted in two channels of the reactor protection system being declared 
inoperable (Channels A and D).  According to the licensee, the currently 
installed setpoints would provide a trip on an axial shape index         
excursion, but may not trip as early as required.  The shape annealing   
factors for Channels B and C were determined to be satisfactory.         
                                                                         
As a result of declaring two of the four channels of the reactor         
protection system inoperable, and in accordance with the Technical       
Specifications, the licensee entered a 48-hour limiting condition for    
operation and reduced reactor power to 70 percent.  One inoperable       
channel was placed in bypass, and the second inoperable channel was      
placed in the tripped condition.  The licensee is performing a more      
detailed review of the annealing factor calculations.                    

Regional Action:

The resident inspectors will continue to monitor the licensee's actions. 

Contact:  Wayne Walker               (402)426-9611
          David Graves               (817)860-8141
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