Headquarters Daily Report

                         AUGUST 04, 1997

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                    REPORT             NEGATIVE            NO INPUT
                    ATTACHED           INPUT RECEIVED      RECEIVED

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REGION IV           û                                      
PRIORITY ATTENTION REQUIRED  MORNING REPORT - HEADQUARTERS AUGUST  4, 1997

MR Number: H-97-0095

                           NRR DAILY REPORT ITEM
                           GENERIC COMMUNICATIONS



NRC Information Notice 97-62: "Unrecognized Reactivity Addition During   
Plant Shutdown," dated August 6, 1997.                                   
                                                                         
The NRC is issuing this information notice to alert addressees to a      
recent incident in which a licensed reactor operator continuously        
inserted control rods to bring the reactor to the subcritical stage and  
then promptly withdrew the rods in order to take the reactor to the      
critical stage and return power to the point of adding heat.             
                                                                         
Technical contacts:  Thomas Koshy, NRR                                   
                     301-415-1176                                        
                                                                         
                     Marc Dapas, RIII                                    
                     (630) 829-9601                                      
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REGION IV  MORNING REPORT     PAGE  2          AUGUST  4, 1997

Licensee/Facility:                     Notification:

Nebraska Public Power District         MR Number: 4-97-0062
Cooper 1                               Date: 08/04/97
Brownville,Nebraska                    Senior Resident Inspector          
Dockets: 50-298
BWR/GE-4                              

Subject: REACTOR STARTUP FOLLOWING OUTAGE                                
         (Also refer to Event 32695)                                     

Reportable Event Number: 32717                         

Discussion:

On August 3, 1997, Cooper Nuclear Station performed a reactor startup.   
The licensee had shut down the unit to troubleshoot and repair the       
torus-to-drywell vacuum breakers.  During the outage, four vacuum        
breakers were found which did not seal when closed. The licensee rebuilt 
and satisfactorily tested all 12 torus-to-drywell vacuum breakers.  As of
8 a.m. on August 4, the Unit was at about 31 percent power and scheduled 
to reach full power later in the day.                                    
                                                                         
On August 4, 1997, at 3:30 a.m., during power ascension, torus level     
exceeded the Technical Specification maximum level during a high pressure
coolant injection pump surveillance.  The licensee entered Technical     
Specification 1.O.J, which requires that the plant be in hot shutdown    
within 6 hours.  At 5:04 a.m., the licensee reduced the torus water level
below the limit, exited Technical Specification 1.O.J, and resumed power 
accession.                                                               

Regional Action:

The resident inspectors observed the shutdown, valve testing, and        
startup.                                                                 

Contact:  Elmo E. Collins            (817)860-8291
          Mary H. Miller             (402)825-3371
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