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Morning Report for January 21, 2000

                       Headquarters Daily Report

                         JANUARY 21, 2000

***************************************************************************
                    REPORT             NEGATIVE            NO INPUT
                    ATTACHED           INPUT RECEIVED      RECEIVED

HEADQUARTERS                           X                   
REGION I                               X                   
REGION II           X                                      
REGION III                             X                   
REGION IV                              X                   
PRIORITY ATTENTION REQUIRED  MORNING REPORT - REGION II  JANUARY 21, 2000

Licensee/Facility:                     Notification:

Tennessee Valley Authority             MR Number: 2-00-0004
Sequoyah 1 2                           Date: 01/21/00
Soddy-Daisy,Tennessee                                                     
Dockets: 50-327,50-328
PWR/W-4-LP,PWR/W-4-LP                 

Subject: UPDATE - UNIT 2 INADVERTENT SAFETY INJECTION AND REACTOR TRIP   

Discussion:

The licensee's troubleshooting activities and corrective actions in      
response to the inadvertent safety injection and reactor trip on         
January 18, 2000, have been completed and Unit 2 achieved criticality on 
January 20, 2000, at 4:04 a.m. (EST).                                    
                                                                         
The licensee's event investigation determined that the technicians that  
were working on vital inverter 2-IV modification wiring, caused a        
momentary loss of power to the inverter (alternate power supply had been 
previously de-energized) which generated a signal to close the main      
feedwater regulating valve to steam generator number 4 (S/G NO.4). The   
subsequent rapid decrease in S/G NO.4 water level generated a low-low    
steam generator level trip signal (2/3 logic) and an automatic reactor   
trip. The licensee also determined that the inadvertent ESF actuation    
(train "A" SI signal) that occurred following the reactor trip was due to
a low steamline pressure (S/G NO.4) signal to the reactor protection     
system (RPS) channels II and IV. The RPS channel IV signal was caused by 
the loss of power to vital inverter 2-IV and the RPS channel II signal   
was due to a malfunctioning steam generator pressure transmitter.        
                                                                         
Reactor power level is currently at 75 percent and the unit is proceeding
to full power operations.                                                

Contact:  PAUL FREDRICKSON           (404)562-4530
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