Headquarters Daily report

                              DECEMBER 21, 1994

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PRIORITY ATTENTION REQUIRED  MORNING REPORT - HEADQUARTERS DEC. 21, 1994

MR Number: H-94-0115

                            NRR DAILY REPORT ITEM
           GENERIC COMMUNICATIONS BRANCH/EVENTS ASSESSMENT BRANCH
                    DIVISION OF OPERATING REACTOR SUPPORT
                    OFFICE OF NUCLEAR REACTOR REGULATION

Subject: N/A

NRC Information Notice 94-85, "Problems with the Latching Mechanism in   
Potter and Brumfield R10-E3286-2 Relays," to be issued December 21, 1994.
                                                                         
The NRC is issuing this information notice to alert addressees to        
problems reported by C&D Charter Power Systems (C&D) in the latching     
mechanism of Potter and Brumfield R10-E3286-2 relays.                    
                                                                         
Technical contacts:  Virgil L. Beaston, NRR                              
                     (301) 504-2989                                      
                                                                         
                     Bill H. Rogers, NRR                                 
                     (301) 504-2945                                      
                                                                         
                                                                         
NRC Information Notice 94-86, "Legal Actions Against Thermal Science,    
Inc., Manufacturer of Thermo-Lag," to be issued December 22, 1994.       
                                                                         
The NRC is issuing this information notice to inform addressees of a     
grand jury indictment of Thermal Science, Inc., and Rubin Feldman,       
President, for allegedly making false statements to the NRC and others   
concerning the fire barrier material known as Thermo-Lag.  In a separate 
legal action, Industrial Testing Laboratories, Inc., and Alan M. Siegel, 
President, pleaded guilty to making and aiding and abetting the making of
false statements concerning Thermo-Lag.                                  
                                                                         
Technical contact:  Edward A. Connell, NRR                               
                    (301) 504-2838                                       
                                                                         
                                                                         
NRC Information Notice 94-87, "Unanticipated Crack in a Particular Heat  
of Alloy 600 Used for Westinghouse Mechanical Plugs for Steam Generator  
Tubes," to be issued December 22, 1994.                                  
                                                                         
The NRC is issuing this information notice to alert addressees to recent 
operating experience affecting the predicted service life of mechanical  
tube plugs fabricated from alloy 600 and supplied by Westinghouse.       
                                                                         
Technical contacts:  Geoffrey P. Hornseth, NRR                           
                     (301) 504-2756                                      
                                                                         
                     Robert A. Hermann, NRR                              
                     (301) 504-2768                                      
                                                                         
                                                                         
NRC Information Notice 94-88, "Inservice Inspection Deficiencies Result  
in Severely Degraded Steam Generator Tubes," to be issued December 23,   
1994.                                                                    
                                                                         
The NRC is issuing this information notice (IN) to alert addressees to   
recent findings from steam generator (SG) tube inspections and           
investigations at Maine Yankee Atomic Power Station (Maine Yankee).  A   
number of tubes were degraded to the point where they potentially no     
longer retained adequate structural margins to sustain the full range of 
normal operating, transient, and postulated accident conditions without  
rupture.  This occurrence is the result of inservice inspection          
deficiencies during past inspections.  On December 7, 1992, NRC informed 
addressees of a similar problem at Arkansas Nuclear One, Unit 2 (ANO 2), 
by issuing NRC IN 92-80, "Operation With Steam Generator Tubes Seriously 
Degraded."                                                               
                                                                         
Technical contact:  Emmett L. Murphy, NRR                                
                    (301) 504-2710